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Publications and reports
related to Serpent development
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Aufiero, M., Cammi, A., Fiorina, C., Leppänen, J., Luzzi, L. and Ricotti, M. (2013a)
"An extended version of the Serpent-2 code to investigate fuel burn-up and core material evolution of the molten salt fast reactor."
J. Nucl. Mat., 441 (2013) 473-486.
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Aufiero, M., Brovchenko, M., Cammi, A., Clifford, I., Geoffroy, O., Heuer, D., Laureau, A., Losa, M., Luzzi, L., Merle-Lucotte, E., Ricotti, M. E. and Rouch, H. (2014)
"Calculating the effective delayed neutron fraction in the molten salt fast reactor: Analytical, deterministic and Monte Carlo approaches."
Ann. Nucl. Energy, 65 (2014) 78-90.
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Aufiero, M., Bidaud, A., Hursin, M., Leppänen, J., Palmiotti, G., Pelloni, S. and Rubiolo, P. (2015)
"A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT."
Ann. Nucl. Energy, 85 (2015) 245-258.
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Aufiero, M. and Fratoni, M. (2016d)
"Testing Advanced Methods for Sensitivity/Uncertainty Analysis in the Monte Carlo Code Serpent."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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Aufiero, M., Palmiotti, G., Salvatores, M. and Sen, S. (2016e)
"Coupled reactors analysis: New needs and advances using Monte Carlo methodology."
Ann. Nucl. Energy, 98 (2016) 218-225.
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Aufiero, M., Martin, M. and Fratoni, M. (2016f)
"XGPT: Extending Monte Carlo Generalized Perturbation Theory capabilities to continuous-energy sensitivity functions."
Ann. Nucl. Energy, 96 (2016) 295-306.
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Aufiero, M., Qiu, Y. and Fratoni, M.(2016g )
"The Iterated Fission Matrix Method."
Trans. Am. Nucl. Soc., 115 (2016) 567-570.
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Aufiero, M., Bidaud, A., Kotlyar, D., Leppänen, J., Palmiotti G., Salvatores, M., Sen S., Shwageraus, E. and Fratoni, M. (2017a)
"New Approaches and Applications for Monte Carlo Perturbation Theory."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Aufiero, M., Fratoni, M., Palmiotti, G. and Salvatores, M. (2017b)
"Continuous Energy Cross Section Adjustment: a New Method to Generalize Nuclear Data Assimilation for a Wider Range of Applications."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Dorval, E. (2013)
"A new method for the calculation of diffusion coefficients with Monte Carlo."
In proc. SNA + MC 2013, Paris, France, Oct. 27-31, 2013.
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| • |
Dorval, E. and Leppänen, J. (2015)
"Monte Carlo current-based diffusion coefficients: Application to few-group constants generation in Serpent."
Ann. Nucl. Energy, 78 (2015) 104-116.
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| • |
Dorval, E. (2016a)
"Directional diffusion coefficients and leakage-corrected discontinuity factors: Implementation in Serpent and tests."
Ann. Nucl. Energy, 87 (2016) 101-112.
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Dorval, E. (2016b)
"A comparison of Monte Carlo methods for neutron leakage at assembly level."
Ann. Nucl. Energy, 87 (2016) 591-600.
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Dorval, E. (2016c)
"A comparative study of leakage and diffusion coefficient models for few-group cross section generation with the Monte Carlo method."
Ann. Nucl. Energy, 90 (2016) 353-363.
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Dorval, E. (2016d)
"Monte Carlo methodologies for neutron streaming in diffusion calculations - Application to directional diffusion coefficients and leakage models in XS generation."
D.Sc. Thesis, Aalto University, 2016.
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Dufek, J. and Valtavirta, V. (2014)
"Time step length versus efficiency of Monte Carlo burnup calculations."
Ann. Nucl. Energy, 72 (2014) 409-412.
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Fridman, E. and Leppänen, J. (2011)
"On the use of the Serpent Monte Carlo code for few-group cross section generation."
Ann. Nucl. Energy, 38 (2011) 1399-1405.
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| • |
Fridman, E. and Leppänen, J. (2012a)
"Revised methods for few-group cross section generation in the Serpent Monte Carlo code."
In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
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| • |
Ikonen, T. (2013a)
"FINIX - fuel behavior model and interface for multiphysics applications - code documentation for version 0.13.9."
VTT-R-06563-13, VTT Technical Research Centre of Finland, 2013.
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| • |
Ikonen, T., Tulkki, V., Syrjälahti, E., Valtavirta, V. and Leppänen, J. (2013b)
"FINIX - fuel behavior model and interface for multiphysics applications."
In proc. TopFuel 2013, Charlotte, NC, Sept. 15-19, 2013.
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| • |
Ikonen, T., Loukusa, H., Syrjälahti, E., Valtavirta, V., Leppänen, J. and Tulkki, V. (2015)
"Module for thermomechanical modeling of LWR fuel in multiphysics simulations."
Ann. Nucl. Energy, 84 (2015) 111-121.
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| • |
Ikonen, T., Syrjälahti, E., Valtavirta, V., Loukusa, H., Leppänen, J. and Tulkki, V. (2016)
"Multiphysics simulation of fast transients with the FINIX fuel behaviour module."
EPJ Nuclear Sci. Technol., 2 (2016) Article 37.
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Isotalo, A. (2009)
"Improved TTA methods for the reactor physics code Serpent."
Special assignment, Helsinki University of Technology, 2009.
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Isotalo, A. (2010)
"Improved time integration methods for burnup calculations with full systems of nuclides."
M.Sc. Thesis, Helsinki University of Technology, 2010.
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Isotalo, A. and Aarnio, P. (2011a)
"Comparison of depletion algorithms for large systems of nuclides."
Ann. Nucl. Energy, 38 (2011) 261-268.
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Isotalo, A. and Aarnio, P. (2011b)
"Higher order methods for burnup calculations with Bateman solutions."
Ann. Nucl. Energy, 38 (2011) 1987-1995.
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Isotalo, A. and Aarnio, P. (2011c)
"Substep methods for burnup calculations with Bateman solution."
Ann. Nucl. Energy, 38 (2011) 2509-2514.
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Isotalo, A., Leppänen, J. and Dufek, J. (2013a)
"Preventing xenon oscillations in Monte Carlo burnup calculations by enforcing equilibrium distribution."
Ann. Nucl. Energy, 60 (2013) 78-85.
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| • |
Isotalo, A. (2013b)
"Computational methods for burnup calculations with Monte Carlo neutronics."
D.Sc. Thesis, Aalto University, 2013.
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Isotalo, A. and Sahlberg, V. (2015a)
"Comparison of Neutronics-Depletion Coupling Schemes for Burnup Calculations."
Nucl. Sci. Eng., 179 (2015) 434-459.
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| • |
Isotalo, A. (2015b)
"Comparison of Neutronics-Depletion Coupling Schemes for Burnup Calculations -- Continued Study."
Nucl. Sci. Eng., 180 (2015) 286-300.
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| • |
Kaltiaisenaho, T. (2014a)
"Statistical tests and the underestimation of variance in Serpent 2."
VTT-R-00371-14, VTT Technical Research Centre of Finland, 2014.
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| • |
Kaltiaisenaho, T. and Leppänen, J. (2014b)
"Analysing the Statistics of Group Constants Generated by Serpent 2 Monte Carlo Code."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Kaltiaisenaho, T. (2016)
"Implementing a photon physics model in Serpent 2."
M.Sc. Thesis, Aalto University, 2016.
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| • |
Kaltiaisenaho, T. (2019)
"Photonuclear Reactions in Serpent 2 Monte Carlo Code."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Kaltiaisenaho, T. (2020)
"Photon transport physics in Serpent 2 Monte Carlo code."
Comp. Phys. Comm., 252 (2020) 107143.
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Leppänen, J. (2005a)
"Diffusion code group constant generation using the Monte Carlo method."
In proc. XII Meeting on Reactor Physics in the Nordic Countries, Halden, Norway, 17-18 May, 2005.
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| • |
Leppänen, J. (2005b)
"A new assembly-level Monte Carlo neutron transport code for reactor physics calculations."
In proc. M&C 2005, Avignon, France, Sept. 12-15, 2005.
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| • |
Leppänen, J. (2006)
"Current status of the PSG Monte Carlo neutron transport code."
In proc. PHYSOR 2006, Vancouver, BC, Canada, Sept. 10-14, 2006.
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| • |
Leppänen, J. (2007a)
"VVER-440 local power peaking experiment benchmark."
VTT-R-02688-07, VTT Technical Research Centre of Finland, 2007.
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| • |
Leppänen, J. (2007b)
"Randomly dispersed particle fuel model in the PSG Monte Carlo neutron transport code."
In proc. M&C + SNA 2007 Monterey, CA, Apr. 15-18, 2007
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| • |
Leppänen, J. (2007c)
"Development of a new Monte Carlo reactor physics code."
D.Sc. Thesis, Helsinki University of Technology, 2007. (VTT Publications 640)
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| • |
Leppänen, J. (2008a)
"PSG status report (March 2008)."
VTT-R-02580-08, VTT Technical Research Centre of Finland, 2008.
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| • |
Leppänen, J. (2008b)
"On the feasibility of a homogenised multi-group Monte Carlo method in reactor analysis."
In proc. PHYSOR 2008, Interlaken, Switzerland, Sept. 14-19, 2008.
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| • |
Leppänen, J. and Pusa, M. (2009a)
"Burnup calculation capability in the PSG2 / Serpent Monte Carlo reactor physics code."
In proc. M&C 2009, Saratoga Springs, NY, May 3-7, 2009.
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| • |
Leppänen, J. (2009b)
"Two practical methods for unionized energy grid construction in continuous-energy Monte Carlo neutron transport calculation."
Ann. Nucl. Energy, 36 (2009) 878-885.
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| • |
Leppänen, J. (2009c)
"On the use of the continuous-energy Monte Carlo method for lattice physics applications."
In proc. INAC 2009, Rio de Janeiro, Brazil, Sept. 27 - Oct. 2, 2009.
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| • |
Leppänen, J., DeHart, M. (2009d)
"HTGR reactor physics and burnup calculations using the Serpent Monte Carlo code."
Trans. Am. Nucl. Soc., 101 (2009) 782-784.
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| • |
Leppänen, J. (2010a)
"Serpent progress report 2009."
VTT-R-01296-10, VTT Technical Research Centre of Finland, 2010.
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| • |
Leppänen, J. (2010b)
"Performance of Woodcock delta-tracking in lattice physics applications using the Serpent Monte Carlo reactor physics burnup calculation code."
Ann. Nucl. Energy, 37 (2010) 715-722.
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| • |
Leppänen, J. (2010c)
"HTGR modeling capabilities in the Serpent Monte Carlo code."
In proc. IYNC-2010, Cape Town, South Africa, Jul. 12-18, 2010.
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| • |
Leppänen, J. (2010d)
"Serpent Monte Carlo Reactor Physics Code."
In proc. 20th AER Symposium on VVER Reactor Physics and reactor safety, Espoo, Finland, Sept. 20-24, 2010.
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| • |
Leppänen, J. (2010e)
"Use of the Serpent Monte Carlo reactor physics code for full-core calculations."
In proc. SNA + MC 2010, Tokyo, Japan, Oct. 17-21, 2010.
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| • |
Leppänen, J. (2011)
"Serpent progress report 2010."
VTT-R-01362-11, VTT Technical Research Centre of Finland, 2010.
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| • |
Leppänen, J. and Isotalo, A. (2012a)
"Burnup calculation methodology in the Serpent 2 Monte Carlo code."
In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
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| • |
Leppänen, J. (2012b)
"Serpent progress report 2011."
VTT-R-05444-12, VTT Technical Research Centre of Finland, 2012.
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| • |
Leppänen, J., Viitanen, T. and Valtavirta, V. (2012c)
"Multi-physics coupling scheme in the Serpent 2 Monte Carlo code."
Trans. Am. Nucl. Soc., 107 (2012) 1165-1168.
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| • |
Leppänen, J. (2013a)
"Development of a dynamic simulation mode in the Serpent 2 Monte Carlo code."
In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
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| • |
Leppänen, J. (2013b)
"Modeling of nonuniform density distributions in the Serpent 2 Monte Carlo code."
Nucl. Sci. Eng., 174 (2013) 318-325.
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| • |
Leppänen, J. (2014a)
"Serpent progress report 2012."
VTT-R-00300-14, VTT Technical Research Centre of Finland, 2014.
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| • |
Leppänen, J., Aufiero, M., Fridman, E., Rachamin, R. and van der Marck, S. (2014b)
"Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code."
Ann. Nucl. Energy, 65 (2014) 272-279.
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Leppänen, J., Mattila, R. and Pusa, M. (2014c)
"Validation of the Serpent-ARES code sequence using the MIT BEAVRS benchmark - Initial core at HZP conditions."
Ann. Nucl. Energy, 69 (2014) 212-225.
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Leppänen, J. and Aufiero, M. (2014d)
"Development of an Unstructured Mesh Based Geometry Model in the Serpent 2 Monte Carlo Code."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Leppänen, J., Valtavirta, V., Viitanen, T. and Aufiero, M. (2014e)
"Unstructured Mesh Based Multi-Physics Interface for CFD Code Coupling in the Serpent 2 Monte Carlo Code."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Leppänen, J. (2014f)
"Development of a CAD Based Geometry Model in Serpent 2 Monte Carlo Code."
Trans. Am. Nucl. Soc., 111 (2014) 663-667.
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| • |
Leppänen, J. (2015a)
"CAD-based Geometry Type in Serpent 2 -- Application in Fusion Neutronics."
In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
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| • |
Leppänen, J., Pusa, M., Viitanen, T., Valtavirta, V. and Kaltiaisenaho, T. (2015b)
"The Serpent Monte Carlo code: Status, development and applications in 2013."
Ann. Nucl. Energy, 82 (2015) 142-150.
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Leppänen, J., Hovi, V., Ikonen, T., Kurki, J., Pusa, M., Valtavirta, V. and Viitanen, T. (2015c)
"The Numerical Multi-Physics project (NUMPS) at VTT Technical Research Centre of Finland."
Ann. Nucl. Energy, 84 (2015) 55-62.
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Leppänen, J. and Mattila, R. (2015d)
"Study on computational performance in generation of cross sections for nodal simulators using
continuous-energy Monte Carlo calculations."
J. Nucl. Sci. Technol., 52 (2015) 945-952. |
| • |
Leppänen, J. and Kaltiaisenaho, T. (2016a)
"Expanding the Use of Serpent 2 to Fusion Applications: Shut-down Dose Rate Calculations."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Leppänen, J., Pusa, M. and Fridman, E. (2016b)
"Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code."
Ann. Nucl. Energy, 96 (2016) 126-136.
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| • |
Leppänen, J. and Mattila, R. (2016c)
"Validation of the Serpent-ARES code sequence using the MIT BEAVRS benchmark – HFP conditions and fuel cycle 1 simulations."
Ann. Nucl. Energy, 96 (2016) 324-331.
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| • |
Leppänen, J. (2017a)
"On the use of delta-tracking and the collision flux estimator in the Serpent 2 Monte Carlo particle transport code."
Ann. Nucl. Energy, 105 (2017) 161-167.
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| • |
Leppänen, J., Kaltiaisenaho, T., Valtavirta, V. and Metsälä, M. (2017b)
"Development of a Coupled Neutron / Photon Transport Mode in the Serpent 2 Monte Carlo Code."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Leppänen, J., Viitanen, T. and Hyvönen, O. (2017c)
"Development of a Variance Reduction Scheme in the Serpent 2 Monte Carlo Code."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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Leppänen, J. (2019a)
"Response Matrix Method–Based Importance Solver and Variance Reduction Scheme in the Serpent 2 Monte Carlo Code."
Nucl. Technol., 205 (2019) 1416-1432.
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Leppänen, J. (2019b)
"Acceleration of Fission Source Convergence in the Serpent 2 Monte Carlo Code Using a Response Matrix Based Solution for the Initial Source Distribution."
Ann. Nucl. Energy, 128 (2019) 63-68.
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Leppänen, J. and Jokipii, M. (2019c)
"Global Variance Reduction Scheme with Self-Adaptive Weight-Window Mesh in the Serpent 2 Monte Carlo Code."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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Pusa, M. and Leppänen, J. (2010)
"Computing the matrix exponential in burnup calculations."
Nucl. Sci. Eng., 164 (2010) 140-150.
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Pusa, M. (2011)
"Rational approximations to the matrix exponential in burnup calculations."
Nucl. Sci. Eng., 169 (2011) 155-167.
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| • |
Pusa, M. and Leppänen, J. (2012)
"An efficient implementation of the Chebyshev rational approximation method (CRAM) for solving the burnup equations."
In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
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| • |
Pusa, M. (2013a)
"Accuracy considerations for Chebyshev rational approximation method (CRAM) in burnup calculations."
In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
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| • |
Pusa, M. (2013b)
"Numerical methods for nuclear fuel burnup calculations."
D.Sc. Thesis, Aalto University, 2013. (VTT Science 32)
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| • |
Pusa, M. and Leppänen, J. (2013c)
"Solving linear systems with sparse Gaussian elimination in the Chebyshev rational approximation method (CRAM)."
Nucl. Sci. Eng., 175 (2013) 250-258.
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| • |
Pusa, M. (2013d)
"Correction to partial fraction decomposition coefficients for Chebyshev rational approximation on the negative real axis."
arXiv:1206.2880v1 [math.NA].
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| • |
Pusa, M. (2014)
"Higher-Order Chebyshev Rational Approximation Method (CRAM)."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Pusa, M. (2016)
"Higher-Order Chebyshev Rational Approximation Method and Application to Burnup Equations."
Nucl. Sci. Eng., 182 (2017) 297-318.
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| • |
Sirén, P. and Leppänen, J. (2016)
"Expanding the use of Serpent 2 to Fusion Applications: Development of a Plasma Neutron Source."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Sirén, P., Varje, J., Äkäslompolo, S., Asunta, O., Giroud, C., Kurki-Suonio, T. and Weisen, H. (2017)
"Versatile fusion source integrator AFSI for fast ion and neutron studies in fusion devices."
Nucl. Fusion, 58 (2017) 016023.
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| • |
Sirén, P., Varje, Weisen, H. and Koskela, T. (2017)
"Synthetic neutron camera and spectrometer in JET based on AFSI-ASCOT simulations."
J. Instrum., 12 (2017) C09010.
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| • |
Sirén, P. (2018)
"Modelling of JET and ITER reactor relevant plasma neutron source for neutronics calculation chain."
D.Sc. Thesis, Aalto University, 2018.
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| • |
Tuominen, R., Valtavirta, V., Peltola, J. and Leppänen, J. (2016)
"Coupling Serpent and OpenFOAM for Neutronics - CFD Multi-physics Calculations."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Tuominen, R., Valtavirta, V. and Leppänen, J. (2018)
"Application of the Serpent–OpenFOAM Coupled Code System to the SEALER Reactor Core."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Tuominen, R., Valtavirta, V. and Leppänen, J. (2019)
"New energy deposition treatment in the Serpent 2 Monte Carlo transport code."
Ann. Nucl. Energy, 129 (2019) 224-232.
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| • |
Valtavirta, V. (2012)
"Designing and implementing a temperature solver routine for Serpent."
M.Sc. Thesis, Aalto University, 2012.
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| • |
Valtavirta, V. (2013a)
"Internal Neutronics-temperature coupling in Serpent 2 -- Reactivity differences resulting from choice of material property correlations."
In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
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| • |
Valtavirta, V., Tulkki, V., Leppänen, J. and Viitanen, T. (2013b)
"The universal fuel performance code interface in Serpent 2."
In proc. TopFuel 2013, Charlotte, NC, Sept. 15-19, 2013.
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| • |
Valtavirta, V., Viitanen, T. and Leppänen, J. (2014a)
"Internal neutronics-temperature coupling in Serpent 2."
Nucl. Sci. Eng., 177 (2014) 193-202.
|
| • |
Valtavirta, V., Ikonen, T., Viitanen, T. and Leppänen, J. (2014b)
"Simulating Fast Transients with Fuel Behavior Feedback Using the Serpent 2 Monte Carlo Code."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Valtavirta, V. (2015)
"Uncertainty Underprediction in Coupled Time-Dependent Monte Carlo Simulations with Serpent 2."
In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
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| • |
Valtavirta, V., Hessan, M. and Leppänen, J. (2016)
"Delayed Neutron Emission Model for Time Dependent Simulations with the Serpent 2 Monte Carlo Code - First Results."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Valtavirta, V., Leppänen, J. and Viitanen, T. (2017a)
"Coupled neutronics–fuel behavior calculations in steady state using the Serpent 2 Monte Carlo code."
Ann. Nucl. Energy, 100 (2017) 50-64.
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| • |
Valtavirta, V. and Leppänen, J. (2017b)
"Estimating the effects of homogenized fuel temperature in group constant generation using Serpent 2."
Ann. Nucl. Energy, 105 (2017) 79-94.
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| • |
Valtavirta, V. and Leppänen, J. (2017c)
"Coupled Burnup Calculations with the Serpent 2 Monte Carlo Code."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Valtavirta, V. (2017d)
"Development and applications of multi-physics capabilities in a continuous energy Monte Carlo neutron transport code."
D.Sc. Thesis, Aalto University, 2017. (VTT Science 150)
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| • |
Valtavirta, V. and Leppänen, J. (2018a)
"Effects of Fuel Temperature History Approximations on Neutronics Properties of a BWR Assembly."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Valtavirta, V. and Leppänen, J. (2018b)
"New Stochastic Substep Based Burnup Scheme for Serpent 2."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Valtavirta, V., Hovi, V., Loukusa, H., Rintala, A., Sahlberg, V., Tuominen, R. and Leppänen, J. (2019)
"Kraken—An Upcoming Finnish Reactor Analysis Framework."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Viitanen, T. (2009)
"Implementing a Doppler-preprocessor of cross section libraries in reactor physics code Serpent."
M.Sc. Thesis, Helsinki University of Technology, 2009.
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| • |
Viitanen, T. and Leppänen, J. (2011a)
"New Data processing features in the Serpent Monte Carlo code."
J. Korean Phys. Soc 59 (2011) 1365-1368.
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| • |
Viitanen, T. (2011b)
"Serpent-ENIGMA - Combining Monte Carlo reactor physics with fuel performance."
VTT-R-06265-11, VTT Technical Research Centre of Finland, 2011.
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| • |
Viitanen, T. and Leppänen, J. (2012a)
"Explicit treatment of thermal motion in continuous-energy Monte Carlo tracking routines."
Nucl. Sci. Eng., 171 (2012) 165-173.
|
| • |
Viitanen, T. and Leppänen, J. (2012b)
"Explicit temperature treatment in Monte Carlo neutron tracking routines -- First results."
In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
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| • |
Viitanen, T and Tulkki, V. (2012c)
"Combining reactor physics and fuel performance calculations."
In proc. TopFuel 2012, Manchester, UK, Sept. 2-6, 2012.
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| • |
Viitanen, T. and Leppänen, J. (2012d)
"Intelligent nuclide selection capability in the reactor physics and inventory calculation code Serpent 2."
In proc. 12IEMPT, Prague, Czech Republic, Sept. 24-27, 2012.
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| • |
Viitanen, T. and Leppänen, J. (2013a)
"Optimizing the implementation of the target motion sampling temperature treatment technique -- How fast can it get?"
In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
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| • |
Viitanen, T. and Leppänen, J. (2014a)
"Target motion sampling temperature treatment technique with elevated basis cross section temperatures."
Nucl. Sci. Eng., 177 (2014) 77-89.
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| • |
Viitanen, T. and Leppänen, J. (2014b)
"Validating the Serpent Model of FiR 1 Triga Mk-II Reactor by Means of Reactor Dosimetry."
EPJ Web of Conferences, 106 (2016) 03010.
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| • |
Viitanen, T., Leppänen, J. and Forget, B. (2014c)
"Target Motion Sampling Temperature Treatment Technique with Track-Length Estimators in OpenMC -- Preliminary Results."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Viitanen, T. (2015a)
"Development of a stochastic temperature treatment technique for Monte Carlo neutron tracking."
D.Sc. Thesis, Aalto University, 2015. (VTT Science 84)
|
| • |
Viitanen, T. and Leppänen, J. (2015b)
"Effect of the target motion sampling temperature treatment method on the statistics and performance."
Ann. Nucl. Energy, 82 (2015) 217-225.
|
| • |
Viitanen, T. and Leppänen, J. (2015c)
"Temperature Majorant Cross Sections in Monte Carlo Neutron Tracking."
Nucl. Sci. Eng., 180 (2015) 209-223.
|
| • |
Viitanen, T. and Leppänen, J. (2016a)
"New Interpolation Capabilities for Thermal Scattering Data in Serpent 2."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Viitanen, T. and Leppänen, J. (2016b)
"Calculating Neutron Dosimeter Activation in VVER-440 Surveillance Chains with Serpent."
In proc. 26th AER Symposium on VVER Reactor Physics and reactor safety, Helsinki, Finland, Oct. 10-14, 2016.
|
| • |
Wendt, B., Kerby, L., Tumulak, A., Leppänen, J. and DeHart, M. (2017)
"Advancement of Functional Expansion Tallies Capabilities in Serpent 2."
Trans. Am. Nucl. Soc., 116 (2017) 552-555.
|
Theses and student projects with Serpent applications
| • |
Ahimsa, M. (2017)
"Design Analysis of Fuel Assembly and Reactor Core of Floating Nuclear Power Plant KLT-40S using SERPENT."
B.Sc. Thesis, Universitas Gadjah Mada, 2017.
|
| • |
Alam, S. (2018)
"The Design of Reactor Cores for Civil Nuclear Marine Propulsion."
Ph.D. Thesis, University of Cambridge, 2018.
|
| • |
Alameri, S. (2015)
"A coupled nuclear reactor thermal energy storage system for enhanced load following operation."
Ph.D. Thesis, Colorado School of Mines, 2015.
|
| • |
Alberti, A.
"Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility."
M.Sc. Thesis, Oregon State University, 2016.
|
| • |
Alhassan, E. (2015a)
"Nuclear data uncertainty quantification and data assimilation for a lead -cooled fast reactor: Using integral experiments for improved accuracy."
Ph.D. Thesis, Uppsala University, 2015.
|
| • |
Andrews, N. (2015)
"Application of advanced fuel concepts for use in innovative pressurized water reactors."
Ph.D. Thesis, Massachusetts Institute of Technology, 2015.
|
| • |
Aufiero, M. (2014b)
"Development of advanced simulation tools for circulating fuel nuclear reactors."
Ph.D. Thesis, Politecnico di Milano, 2014.
|
| • |
Aures, A. (2012)
"Nuklidinventarbestimmung eines gesamten Leichtwasserreaktorkerns vom Typ Konvoi im Gleichgewichtszustand unter Anwendung des Reaktorphysik-Programms Serpent."
Diploma Thesis, RWTH Aachen University, 2012 (in German).
|
|
Bae, J. (2018)
"Fuel cycle transition simulation capabilities in CYCLUS."
M.Sc. Thesis, University of Illinois, 2018.
|
| • |
Baldova, D. (2014)
"Feasibility study on high-conversion Th-U233 fuel cycle for current generation of PWRs."
Ph.D. Thesis, Technical University of Prague, 2014.
|
| • |
Bao, J. (2016)
"Development of the model for the multiphysics analysis of Molten Salt Reactor Experiment using GeN-Foam code."
M.Sc. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2016.
|
| • |
Barray, C. (2012)
"Monte Carlo simulation of a nuclear research reactor type TRIGA with Serpent code."
Internship Report, Aalto University, 2012.
|
| • |
Bean, M. (2011)
"Computational neutronics analysis of TRIGA reactors during power pulsing."
B.Sc. Thesis, Massachusetts Institute of Technology, 2011.
|
| • |
Bartel, J. (2019)
"Analysis and Improvement of the bRAPID Algorithm and its Implementation."
M.Sc. Thesis, Virginia Tech, 2019.
|
| • |
Beltjens, E. (2017)
"Modelling of the low-void SFR core during ULOF with spatial kinetics."
M.Sc. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2017.
|
| • |
Bergmann, R. (2015)
"The Development of WARP - A Framework for Continuous Energy Monte Carlo Neutron Transport in General 3D Geometries on GPUs."
Ph.D. Thesis, University of California, Berkeley, 2015.
|
| • |
Bianchini, P. (2017)
"Computational features of neutronics and thermal hydraulics coupled simulations."
M.Sc. Thesis, Politecnico di Milano, 2017.
|
| • |
Blanco, J. (2016)
"Triga Reactor calculations using Serpent 2."
Dipl. Eng. Thesis, Balseiro Institute, 2016 (in Spanish).
|
| • |
Borowiec, K. (2016)
"Investigation of temperature reactivity coefficient in EOLE reactor."
B.Sc. Thesis, Warsaw University of Technology, 2016.
|
| • |
Cai, L. (2015)
"Condensation and homogenization of cross sections for the deterministic transport codes with Monte Carlo method : Application to the GEN IV fast neutron reactors."
Ph.D. Thesis, Université Grenoble Alpes, 2015.
| • |
Carbol, S. (2017)
"Development of a hybrid neutron transport method in 2 energy groups."
M.Sc. Thesis, Chalmers University of Technology, 2017.
|
| • |
Castagna, C. (2014)
"Modellizzazione al simulatore delle condizioni di criticità del reattore TRIGA Mark II a diversi livelli di potenza."
M.Sc. Thesis, University of Milano-Bicocca, 2014 (in Italian).
|
| • |
Changizi, S. (2012)
"Neutronic Analysis of the Multipurpose Hybrid Research Reactor for High-tech Applications (MYRRHA) with a Monte Carlo Code SERPENT."
M.Sc. Thesis, Royal Institute of Technology, 2012.
|
| • |
Chersola, D. (2016)
"Application of new neutronic and burnup Monte Carlo based codes to the study of nuclear fuel cycles for GFR and VVER systems."
Ph.D. Thesis, University of Genova, 2016.
|
| • |
Cywinski, J. (2016)
"Study of the re-criticality potential during the ex-vessel phase of severe accident in a Boiling Water Reactor."
M.Sc. Thesis, Warsaw University of Technology, 2017.
|
| • |
Descotes, M. (2011)
"Reactor Physics of a Deep-burner Prismatic Core for VHTR."
M.Sc. Thesis, École Polytechnique de Montréal, 2011.
|
| • |
De Lorenzo, M. (2015)
"Implementation of a Full 3D Neutronic Model for Myrrha in RELAP5-3D using Nestle."
M.Sc. Thesis, Politecnico di Torino, 2015.
|
| • |
Demers, Z. (2017)
"Comparative Safety Evaluation of Thorium Fuel to Natural Uranium Fuel in a CANDU 6 Reactor."
M.Sc. Thesis, McMaster University, 2017.
|
| • |
DeWitte, J. (2014)
"Maximizing nuclear power plant performance via mega-uprates and subsequent license renewal."
Ph.D. Thesis, Massachusetts Institute of Technology, 2014.
|
| • |
Díez Fernández, G. (2012)
"Safety aspects of Ceramic Fully Encapsulated fuel for Light Water Reactors."
M.Sc. Thesis, Universitat Politècnica de Catalunya (UPC) / Royal Institute of Technology, 2012.
|
| • |
Duerigen, S. (2013)
"Neutron Transport in Hexagonal Reactor Cores Modeled by Trigonal-Geometry Diffusion and Simplified P3 Nodal Methods."
Ph.D. Thesis, Karlsruhe Institute of Technology, 2013.
|
| • |
Elgin, K. (2014)
"A study of the feasibility of 99Mo production inside the TU Delft Hoger Onderwijs Reactor."
B.Sc. Thesis, Technical University of Deflt, 2014.
|
| • |
Eloranta, K. (2013)
"RBMK-koereaktorin mallintaminen."
B.Sc. Thesis, Lappeenranta University of Technology, 2013 (in Finnish).
|
| • |
Eriksson, M. (2013)
"Förutsättningarna för ett parallellt generation IV system vid svensk nybyggnation av kärnkraft. The prospects for a parallel generation IV reactor in the swedish nuclear system."
B.Sc. Thesis, Uppsala University, 2013 (in Swedish).
|
| • |
Falaakh, D. (2016)
"Neutronic Analysis of Reduced Moderation Boiling Water Reactor 1050 MWt."
B.Sc. Thesis, Universitas Gadjah Mada, 2016.
|
| • |
Fernández Navarro, A. (2014)
"Impact of fusion neutrons on helium production in beryllium and tungsten, and tritium breeding in ITER and DEMO."
M.Sc. Thesis, Aalto University, 2014.
|
| • |
Fredriksson, P. (2014)
"Determination of Radial Power Profiles in Thorium-Plutonium Mixed Oxide Fuel Pellets."
M.Sc. Thesis, Chalmers University of Technology, 2014.
|
| • |
Garcia, R. (2012)
"A Paranetric Study on Core Performance of Sodium Fast Reactors Using SERPENT Code."
M.Sc. Thesis, Royal Institute of Technology, 2012.
|
| • |
Garcia Domínguez, C. (2013)
"Generation of nuclear data for Lead-cooled Fast Reactor using the Monte Carlo method."
M.Sc. Thesis, Politecnico di Torino, Torino, 2013.
|
| • |
Gentry, C. (2016)
"Development of a Reactor Physics Analysis Procedure for the Plank-Based and Liquid Salt-Cooled Advanced High Temperature Reactor."
Ph.D. Thesis, University of Tennessee, 2012.
|
| • |
Ghasabyan, L. (2013)
"Use of Serpent Monte Carlo code for development of 3D full-core models of Gen-IV fast-spectrum reactors and preparation of group constants for transient analyses with PARCS/TRACE coupled system."
M.Sc. Thesis, Royal Institute of Technology, 2013.
|
| • |
Giudicelli, G. (2017)
"Achievable power uprates in pressurized water reactors using uranium nitride fuel."
M.Sc. Thesis, Massachusetts Institute of Technology, 2017.
|
| • |
Gorman, P. (2016)
"Design and Analysis of Thorium-fueled Reduced Moderation Boiling Water Reactors."
Ph.D. Thesis, University of California, Berkeley, 2016.
|
| • |
Gottfridsson, F. (2010)
"Simulation of Reactor Transient and Design Criteria of Sodium-cooled Fast Reactors Simulation of Reactor Transient and Design Criteria of Sodium-cooled Fast Reactors."
B.Sc. Thesis, Uppsala University, 2010.
|
| • |
Grodzki, M. (2017)
"Neutronic analysis of battery - type high temperature gas-cooled reactor."
M.Sc. Thesis, Warsaw University of Technology, 2017.
|
| • |
Guglielmelli, A. (2015)
"Calcoli di sezioni d'urto efficaci di riflettore in sistemi PWR di terza generazione."
Ph.D. Thesis, University of Bologna, 2015 (in Italian).
|
| • |
Hakim, A. (2017)
"Fuel Assembly Design of Small PWR with Uranium Mononitride Fully Ceramic Microencapsulated Fuel using SCALE and SERPENT."
B.Sc. Thesis, Universitas Gadjah Mada, 2017.
|
| • |
Hall, A (2015)
"Homogenization Methods for Full Core Solution of the Pn Transport Equations with 3-D Cross Sections."
Ph.D. Thesis, University of Michigan, 2015.
|
| • |
Halla-Aho, L (2013)
"Simulation of the Interaction Mean Free Path Between Neutrons and TRISO Particles."
B.Sc. Thesis, Lappeenranta University of Technology, 2013.
|
| • |
Hanlon, B. (2015)
"Validation of the use of low enriched uranium as a replacement for highly enriched uranium in US submarine reactors."
M.Sc. Thesis, Massachusetts Institute of Technology, 2015.
|
| • |
Harris, A. (2013)
"Heavy water as a thorium breeder reactor coolant."
M.Sc. Thesis, University of Cambridge, 2013.
|
| • |
Harrisson, G. (2015)
"Calculation of a Canadian SCWR fuel channel taking into account the conditions of the materials and the axial coupling."
Ph.D. Thesis, École Polytechnique de Montréal, 2015.
|
| • |
Hassan, S. (2011)
"Spatial dependence of reactivity coefficients."
M.Sc. Thesis, Royal Institute of Technology, 2011.
|
| • |
Helgesson, P. (2013)
"UO-2 vs MOX: Propagated nuclear data uncertainty with burnup using Fast Total Monte Carlo."
B.Sc. Thesis, Uppsala University, 2013.
|
| • |
Herman, B. (2011)
"Cross section generation strategy for high conversion light water reactors."
M.Sc. Thesis, Massachusetts Institute of Technology, 2011.
|
| • |
Hermawan, D. (2016)
"Analysis of Fuel Assembly Design in Small PWR using Uranium Nitride-Based Fully Ceramic Microencapsulated Fuel on Soluble Boron Free Operational Condition."
B.Sc. Thesis, Universitas Gadjah Mada, 2016.
|
| • |
Hidayatullah, R. (2014)
"A Novel Research Reactor Concept Based on Coated Particle Fuel."
M.Sc. Thesis, Korea Advanced Institute of Science and Technology, 2014.
|
| • |
Hiscox, B. (2018)
"Analysis and Optimization of a New Accident Tolerant Fuel Called Fuel-in-Fibers."
M.Sc. Thesis, Massachusetts Institute of Technology, 2018.
|
| • |
Hombourger, B. (2018)
"Conceptual Design of a Sustainable Waste Burning Molten Salt Reactor."
Ph.D. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2018.
|
| • |
Hrabar, Y. (2019)
"Development, benchmarking and validation of the Advanced Nuclear Fuel Cycle Simulator FANCSEE and advanced use of Monte Carlo methods in nuclear reactor calculations."
M.Sc. Thesis, University Paris-Saclay, 2019.
|
| • |
Hyvärinen, J-P. (2012)
"HTR-PROTEUS-reaktorin mallintaminen."
B.Sc. Thesis, Lappeenranta University of Technology, 2012 (in Finnish).
|
| • |
Hyvönen, O. (2015)
"Finding optimal reconstruction parameters for cross section libraries used with Serpent 2."
B.Sc. Thesis, Aalto University, 2015.
|
| • |
Hyvönen, O. (2019)
"Variance reduction methods in Monte Carlo particle transport simulations."
Special assignment, Aalto University, 2019.
|
| • |
Ignaczak, P. (2016)
"Monte Carlo Simulation of the AP1000 Nuclear Reactor."
M.Sc. Thesis, Warsaw University of Technology, 2017.
|
| • |
Inkinen, P. (2009)
"Implementation of nodal diffusion model into APROS."
M.Sc. Thesis, Helsinki University of Technology, 2009.
|
| • |
Ivanov, A. (2015)
"High Fidelity Monte Carlo Based Reactor Physics Calculations."
Dr.-Ing. Thesis, Karlsruhe Institute of Technology, 2015.
|
| • |
Jo, Y., Kong, C., Cherezov, A., Lee, D. (2019)
"Sensitivity and Uncertainty Analysis Capability in MCS for UAM Benchmark."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
|
| • |
Johns, J. (2014)
"Physics-based Predictive Time Propagation Method for Monte Carlo Coupled Depletion Simulations."
Ph.D. Thesis, Texas A&M University, 2014.
|
| • |
Juutilainen, P. (2009)
"Burnup credit benchmark calculation with Monte Carlo method."
Special assignment, Helsinki University of Technology, 2009. (VTT-R-06819-09)
|
| • |
Kaartinen, D. (2019)
"Laskentakoodien Vertailu Säteilymittarien Sijoitus- ja Suoritusanalyysissä."
M.Sc. Thesis, Lappeenranta University of Technology, 2019 (in Finnish).
|
| • |
Kalinainen, T. (2016)
"Modelling of Decay Heat with Exponential Functions in Serpent 2."
Special assignment, Aalto University, 2016.
|
| • |
Karlsson, D. and Kollberg, E. (2015)
"Säkerhetsegenskaper hos en rymdreakto."
B.Sc. Thesis, Royal Institute of Technology, 2015 (in Swedish).
|
| • |
Karriem, V. (2016)
"The Development of a Thermal Hydraulic Feedback Mechanism with a Quasi-fixed Point Iteration Scheme for Control Rod Position Modeling for the TRIGSIMS-TH Application."
Ph.D. Thesis, Pennsylvania State University, 2016.
|
| • |
Kelm, C. (2012)
"Auswirkung einer Langzeitzwischenlagerung auf abgebrannten DWR Kernbrennstoff und Szenarien zur zukünftigen Wiederverwendung."
Diploma Thesis, RWTH Aachen University, 2012 (in German).
|
| • |
Kim, H. (2015)
"Static and transient analysis of Molten Salt Reactor Experiment using SERPENT-2/TRACE/PARCS code."
M.Sc. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2015.
|
| • |
Kim, W. (2013a)
"Improvement of CANDU safety parameters by using CANFLEX."
M.Sc. Thesis, Korea Advanced Institute of Science and Technology, 2013.
|
| • |
Kim, Y. (2012)
"Preliminary Analysis of Neutronic Parameters of European Lead Cooled Training Reactor (ELECTRA)."
M.Sc. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2012.
|
| • |
Knebel, M. (2017)
"Advanced high-fidelity reactor simulators based on neutron transport and subchannel methodologies."
Dr.-Ing. Thesis, Karlsruhe Institute of Technology, 2017.
|
| • |
Kotlyar, D. (2013)
"Development of Advanced Burnup-Thermal Hydraulic Coupling Methods for Monte Carlo Codes."
Ph.D. Thesis, Ben-Gurion University of the Negev, 2013.
|
| • |
Kubinski, W. (2017)
"Neutronic analysis of a liquid sodium cooled fast nuclear reactor core using a Monte Carlo method.",
B.Sc. Thesis, Warsaw University of Technology, 2017 (in Polish).
|
| • |
Kuopanportti, J. (2009)
"Radkowsky-nipun suorituskyky ja vaikutus neutroniikkaan tyypillisessä painevesireaktorissa."
B.Sc. Thesis, Helsinki University of Technology, 2009 (in Finnish).
|
| • |
Kuopanportti, J. (2010)
"CASMO-4E simulations of the Radkowsky Thorium Fuel concept."
Special assignment, Aalto University, 2010.
|
| • |
Kähärä, R. (2015)
"Simulating gamma transport with Serpent."
B.Sc. Thesis, Aalto University, 2015.
|
| • |
Laaksoviita, T. (2013)
"Simplified modelling of a fresh pressurized water reactor core by diffusion theory."
B.Sc. Thesis, Aalto University, 2013.
|
| • |
Lago, D. (2017)
"Development of an application programming interface for depletion analysis (APIDA)."
Ph.D. Thesis, Georgia Institute of Technology, 2017.
|
| • |
Laureau, A. (2015)
"Développement de modèles neutroniques pour le couplage thermohydraulique du MSFR et le calcul de paramètres cinétiques effectifs."
Ph.D. Thesis, Université Grenoble Alpes, 2015 (in French).
|
| • |
Laurier, A. (2016)
"Implementation of the SPH procedure within the Moose finite element framework."
M.Sc. Thesis, École Polytechnique de Montréal, 2016.
|
| • |
Lázaro, A. (2014)
"Development, Assessment and Application of Computational Tools for Design Safety Analysis of Liquid Metal Cooled Fast Breeder Reactors."
Ph.D. Thesis, University of Valencia, 2014.
|
| • |
Le Meur, L. (2018)
"Etude des propriétés de désintégration bêta de noyaux exotiques d'intérêts pour la physique des réacteurs, la structure nucléaire et l'astrophysique nucléaire, à l'aide de la technique de Spectroscopie Gamma par Absorption Totale (TAGS)."
Ph.D. Thesis, University of Nantes, 2018.
|
| • |
Lovecký, M. (2017)
"Increasing the effciency of nuclear fuel using burnable absorbers."
D.Sc. Thesis, University of West Bohemia, 2017.
|
| • |
Lu, Q. (2014)
"Stability analysis of a natural circulation lead-cooled fast reactor."
M.Sc. Thesis, University of Illinois, 2014.
|
| • |
Luszczek, K. (2015)
"Validation and Benchmarking of Westinghouse Lattice Physics Methods."
M.Sc. Thesis, Royal Institute of Technology, 2015.
|
| • |
Lyons, J. (2013)
"Reactor physics model of the advanced test reactor using TRIGA fuel through application of Serpent 2."
M.Sc. Thesis, Oregon State University, 2013.
|
| • |
Lyu, J. (2016)
"(An) innovative way of Co-60 production in CANDU6 reactors."
M.Sc. Thesis, Korea Advanced Institute of Science and Technology, 2016.
|
| • |
Mahjoub, M. (2016)
"Développement d'une méthode de Monte Carlo dépendante dutemps et application au réacteur de type CANDU-6."
Ph.Dc. Thesis, École Polytechnique de Montréal, 2016 (in French).
|
| • |
Mardus-Hall, R., Ho, M., Pastrello, A. and Yeoh, G. (2020)
"3-Way coupled thermohydraulic-discrete element-neutronic simulation of solid fuel, molten salt reactor."
Ann. Nucl. Energy, 135 (2020) 106973.
|
| • |
Martin, N. (2011)
"Application de la méthode des sous-groupes au calcul Monte-Carlo multigroupe."
Ph.D. Thesis, École Polytechnique de Montréal, 2011 (in French).
| • |
Macdonald, R. (2014)
"Investigation and design of a secure, transportable fluoride-salt-cooled high-temperature reactor (TFHR) for isolated locations."
M.Sc. Thesis, Massachusetts Institute of Technology, 2014.
|
| • |
Mehta, V. (2018)
"Spectral Shift Operated SMAHTR to Improve Cycle Length and Discharge Burnup Continuously."
M.Sc. Thesis, Georgia Institute of Technology, 2018.
|
| • |
Metsälä, M. (2016)
"Accurate Heat Deposition Calculations in Nuclear Reactors Using Monte Carlo Neutron and Photon Transport."
Special assignment, Aalto University, 2016.
|
| • |
Mettälä, J. (2012)
"Vaikutusalakirjastojen muodostaminen Serpent-ARES-laskentaketjussa."
M.Sc. Thesis, Lappeenranta University of Technology, 2012 (in Finnish).
|
| • |
Mieloszyk, A. (2015)
"Assessing thermo-mechanical performance of ThO2 and SiC clad light water reactor fuel rods with a modular simulation tool."
Ph.D. Thesis, Massachusetts Institute of Technology, 2015.
|
| • |
Mikolajczak, A. (2016)
"Neutronic analysis of Sodium-cooled Fast Reactor ores with Various Fuel Types."
M.Sc. Thesis, Warsaw University of Technology, 2017.
|
| • |
Moberg, K. (2012)
"An investigation of fuel cycles and material flows for a lead-cooled fast reactor using the Monte Carlo code Serpent."
B.Sc. Thesis, Uppsala University, 2012.
|
| • |
Muszynski, D. (2017)
"Testing accuracy of rectangular diffusion model of Maria reactor."
M.Sc. Thesis, Warsaw University of Technology, 2017.
|
| • |
Nikitin, E. (2019)
"Extension of the nodal code DYN3D to SFR applications ."
Ph.D. Thesis, École Polytechnique Fédérale de Lausanne, 2018.
|
| • |
Obrebski, P. (2017)
"The Beginning of Cycle Monte Carlo 3 D Simulations of the AP1000 Core."
M.Sc. Thesis, Warsaw University of Technology, 2017.
|
| • |
Ochoa, R. (2014)
"Core physics and safety analysis of Generation-IV Sodium Fast Reactors using existing and newly developed computational tools."
Ph.D. Thesis, Universidad Politécnica de Madrid, 2014.
|
| • |
Panadero, A. (2014)
Static neutronic, thermal-hydraulic, and fuel performance analysis of the ASTRID Sodium-cooled Fast Reactor core."
M.Sc. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2014.
|
| • |
Patel, V. (2012)
"A Multi-Modular Neutronically Coupled Power Generation System."
M.Sc. Thesis, Texas A&M University, 2012.
|
| • |
Pereira, G. (2018)
"Applying a nodal diffusion-micro depletion sequence for high-fidelity analysis of sodium cooled fast reactors."
M.Sc. Thesis, Georgia Institute of Technology, 2018.
|
| • |
Pettersen, E. (2016)
Coupled multi-physics simulations of the Molten Salt Fast Reactor using coarse-mesh thermal-hydraulics and spatial neutronics."
M.Sc. Thesis, Université Paris-Saclay, 2016.
|
| • |
Potapczyk, K. (2016)
"Potential Re-Criticality of BWR Core During Re- Flooding Phase of Sever Accident."
M.Sc. Thesis, Warsaw University of Technology, 2017.
|
| • |
Preciado, M. (2014)
"Development of a KONVOI PWR Core Model for Coupled TRACE/PARCS Simulations."
B.Sc. Thesis, Universitat Polytecnica de Valencia, 2014.
|
| • |
Quinteros, F. (2016)
"RA-10 reactor modelling using Serpent code."
Dipl. Eng. Thesis, Balseiro Institute, 2016 (in Spanish).
|
| • |
Qvist, S. (2013)
"Core design and safety of large liquid metal cooled fast breeder reactors."
Ph.D. Thesis, University of California Berkeley, 2013.
|
| • |
Rais, A. (2018)
"Performance assessment of a 3-D steady-state and spatial kinetics model for the CROCUS reactor."
Ph.D. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2018.
|
| • |
Ramey, K. (2017)
"Development of serpent-based methods for I2S-LWR depletion modeling and sensitivity studies."
M.Sc. Thesis, Georgia Institute of Technology, 2017.
|
| • |
Raouafi, Haykel (2017)
"Simulation de mécanismes de contrôle de la réactivité inclinés du réacteur SCWR-canadien en utilisant les codes DRAGON-5 et DONJON-3."
M.Sc. Thesis, École Polytechnique de Montréal, 2017 (in French).
|
|
| • |
Raub, S. (2011)
"Transient behaviour in a BWR with Hafnium Cladding."
M.Sc. Thesis, Royal Institute of Technology, 2011.
|
|
| • |
Rawlins, S. (2018)
"Feasibility and Parameterization of Small-scale Low-Enriched Uranium Nuclear Thermal Propulsion."
M.Sc. Thesis, Korea Advanced Institute of Science and Technology, 2018.
|
| • |
Reiter, C. (2019)
"A model system for transient calculations for research reactors with a compact core."
Ph.D. Thesis, Technische Universität München, 2019.
|
| • |
Richard, J. (2016)
"Design optimization and analysis of a fluoride salt cooled high temperature test reactor for accelerated fuels and materials testing and nonproliferation and safeguards evaluations."
Ph.D. Thesis, Massachusetts Institute of Technology, 2016.
|
| • |
Rintala, A. (2012)
"Effect of temperature discretization on the results of neutronics calculations."
B.Sc. Thesis, Aalto University, 2012.
|
| • |
Rintala, A. (2013)
"Error of multigroup energy discretization in fast reactors."
Special assignment, Aalto University, 2012.
|
| • |
Rintala, A. (2015)
"Development and validation of Apros multigroup nodal diffusion model."
M.Sc. Thesis, Aalto University, 2015.
|
| • |
Rintala, V. (2011)
"Monte Carlo -reaktorifysiikkalaskennan ja laskennallisen virtausmekaniikan kytkentä kuulakekoreaktorissa."
M.Sc. Thesis, Lappeenranta University of Technology, 2011 (in Finnish).
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Rykhlevskii, A. (2018)
"Advanced online fuel reprocessing simulation for thorium-fueled molten salt breeder reactor."
M.Sc. Thesis, University of Illinois, 2018.
|
| • |
Sahlberg, V. (2013)
"Comparison of coupling schemes for Monte Carlo burnup calculations."
B.Sc. Thesis, Aalto University, 2013.
|
| • |
Sahlberg, V. (2014)
"Development of Serpent 2 – TRAB3D code sequence."
Special assignment, Aalto University, 2014. (VTT-R-04538-14)
|
| • |
Sahlberg, V. (2015)
"Validating Pin Power Reconstruction Module with Serpent 2 – TRAB3D Code Sequence."
Special assignment, Aalto University, 2015. (VTT-R-04065-15)
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| • |
Sahlberg, V. (2016a)
"Modelling of axial discontinuities in reactor cores with Serpent 2 - TRAB3D code sequence."
M.Sc. Thesis, Aalto University, 2016.
|
| • |
Sallinen, I. (2017)
"Sensitivity testing of the fusion neutron calculation chain consisting of ASCOT and AFSI."
B.Sc. Thesis, Aalto University, 2017.
|
| • |
Samaropoulos, I. (2013)
"Development of SERPENT based equilibrium fuel cycle procedure EQL0D."
M.Sc. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2013.
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| • |
Shapiro, R. (2014)
"Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel."
M.Sc. Thesis, Pennsylvania State University, 2014.
|
| • |
Salah, S. (2011)
"Spatial dependence of reactivity coefficients."
B.Sc. Thesis, Royal Institute of Technology, 2011.
|
| • |
Sartori, A. (2015)
"Reduced order methods: applications to nuclear reactor core spatial dynamics."
Ph.D. Thesis, Politecnico di Milano, 2015.
|
| • |
Shirvan, K. (2013)
"Development of optimized core design and analysis methods for high power density BWRs."
Ph.D. Thesis, Massachusetts Institute of Technology, 2013.
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| • |
Scherr, J. (2016)
"Fast Spectrum Material’s Testing Reactor with Variable Energy Spectra to Support Advanced Reactors Program and Light Water Reactor Sustainability Program R&D."
M.Sc. Thesis, Texas A&M University, 2016.
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| • |
Schäfer, K. (2013a)
"Simulation des Erstkritikalitätsexperimentes des THTR-300 unter Anwendung des Reaktorphysik-Programms Serpent."
Minor Thesis, RWTH Aachen University, 2013 (in German).
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| • |
Schäfer, K. (2013b)
"Simulation kritischer Benchmarkexperimente mit einfacher Geometrie unter Anwendung des Reaktorphysik-Programms Serpent."
Minor Thesis, RWTH Aachen University, 2013 (in German).
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| • |
Schäfer, K. (2014)
"Untersuchungen zur Qualität der Graphit-Wirkungsquerschnitte anhand von Benchmarkexperimenten."
Diploma Thesis, RWTH Aachen University, 2014 (in German).
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| • |
Scriven, M. (2015)
"Senstivity of Lattice Physics Modelling of the Canadian PT-SCWR to Changes in Lateral Coolant Density Gradients in a Channel."
M.Sc. Thesis, McMaster University, 2015.
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| • |
Seppälä, M. (2008)
"Neutronic and Thermal-hydraulic Modelling of High Performance Light Water Reactor."
M.Sc. Thesis, Helsinki University of Technology, 2008.
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| • |
Skwarcan-Bidakowski, A. (2017)
"Nuclear reactor core model for the advanced nuclear fuel cycle simulator FANCSEE. Advanced use of Monte Carlo methods in nuclear reactor calculations."
B.Sc. Thesis, Uppsala University, 2017.
|
| • |
Sukjai, Y. (2018)
"Fuel performance modeling of high burnup mixed oxide fuel for hard spectrum LWRs."
Ph.D. Thesis, Massachusetts Institute of Technology, 2018.
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| • |
Suvdantsetseg, E. (2014b)
"Neutronics and Transient Analysis of a Small Fast Reactor Cooled with Natural Circulation of Lead: ELECTRA: European Lead Cooled Training Reactor."
Ph.D. Thesis, Royal Institute of Technology, 2014.
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| • |
Svanström, S. (2016)
"Load following with a passive reactor core using the SPARC design."
B.Sc. Thesis, Uppsala University, 2016.
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| • |
Taavitsainen, A. (2016)
"CFENSS-SRS method for the uncertainty analysis of nuclear fuel and neutronics."
M.Sc. Thesis, Aalto University, 2016.
|
| • |
Tantillo, F. (2013)
"Two dimensional extension of the integral neutronic transport code TOTMOS."
Laurea Magistrale Ingegneria Energetica e Nucleare, Universita di Palermo, 2013.
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| • |
Templeton, J. (2015)
"SERPENT Modeling of the Transient Reactor Test Facility and Comparison with Measured Experimental Data."
M.Sc. Thesis, University of New Mexico, 2015.
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| • |
Tuominen, R. (2015)
"Coupling Serpent and OpenFOAM for neutronics – CFD multi-physics calculations."
M.Sc. Thesis, Aalto University, 2015.
|
| • |
Vitullo, F. (2017)
"Statistical burnup distribution of moving pebbles in HTR-PM reactor."
M.Sc. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2017.
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| • |
Westlund, M. (2019)
"Monte Carlo Simulations of Bowing Effects Using Realistic Fuel Data in Nuclear Fuel Assemblies."
M.Sc. Thesis, Uppsala University, 2019.
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| • |
Wendt, B. (2018)
"Functional Expansions Methods: Optimizations, Characterizations, and Multiphysics Practices."
Ph.D. Thesis, Idaho State University, 2018.
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| • |
Wolniewicz, P. (2012)
"A feasibility study of coolant void detection in a lead-cooled fast reactor using fission chambers."
Lic.Sc. Thesis, Uppsala University, 2012.
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| • |
Wolniewicz, P. (2014)
"Development of a Methodology for Detecting Coolant Void in Lead-cooled Fast Reactors by Means of Neutron Measurements."
D.Sc. Thesis, Uppsala University, 2014.
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| • |
Wrobel, J. (2016)
"Monte Carlo simulations of the EPR nuclear reactor."
M.Sc. Thesis, Warsaw University of Technology, 2017.
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| • |
Wyant, T. (2012a)
"Numerical study of error propagation in Monte Carlo depletion simulations."
M.Sc. Thesis, Georgia Institute of Technology, 2012.
|
|
Wu, X. (2013)
"Coupling of system thermal-hydraulics and Monte-Carlo method for a consistent thermal-hydraulics-reactor physics feedback."
M.Sc. Thesis, University of Illinois, 2013.
|
| • |
Yi, H., Demaziere, C., Vinai, P. and Leppänen, J. (2019)
"Development and Test of a Hybrid Probabilistic-Deterministic Framework Based on the Interface Current Method."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Younker, I. (2015)
"Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors."
M.Sc. Thesis, Pennsylvania State University, 2015.
|
| • |
Younan, S. (2017)
"Comparative study of accident-tolerant fuel for a CANDU lattice."
M.Sc. Thesis, McMaster University, 2017.
|
| • |
Yu, H. (2014)
"Low-boron OPR1000 core based on the BigT burnable absorber."
M.Sc. Thesis, Korea Advanced Institute of Science and Technology, 2014.
|
| • |
Zhang, Y. (2011)
"Transmutation of Americium in Fast Neutron Facilities."
Lic.Sc. Thesis, Royal Institute of Technology, 2011.
|
| • |
Zhang, Y. (2012)
"Transmutation of Am in sodium fast reactors and accelerator driven systems."
D.Sc. Thesis, Royal Institute of Technology, 2012.
|
| • |
Zebryk, A. (2016)
"Neutronic Analysis of the subcritical reactor MYRRHA with a Code SERPENT."
B.Sc. Thesis, Warsaw University of Technology, 2017 (in Polish).
|
| • |
Zilly, A. (2014)
"Modellierung und Simulation der HTR-Experimente am Siemens Argonaut-Reaktor in Graz."
Minor Thesis, RWTH Aachen University, 2014 (in German).
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Publications and reports related to Serpent applications
| • |
Abdelhameed, A., Nguyen, X., Lee, J. and Kim, Y. (2018)
"Feasibility of passive autonomous frequency control operation in a Soluble-Boron-Free small PWR."
Ann. Nucl. Energy, 116 (2018) 319-333.
|
| • |
Abdo, M., Elzohery, R. and Roberts, J. (2018)
"Data-Driven Surrogate Model to Predict Isotopic Composition Using Dynamic Mode Decomposition."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Abrate, N., Dulla, S., Ravetto, P. and Bruna, G. (2018)
"Assessment of Numerical Methods for the Evaluation of Higher-order Harmonics in Diffusion Theory."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Abrate, N., Bruna, G., Dulla, S. and Ravetto, P. (2019)
"Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory."
Ann. Nucl. Energy, 128 (2019) 455-470.
|
| • |
Agung, A. (2016)
"Neutronic assessment on the use of advanced coated particles in a fluidized bed nuclear reactor."
J. Eng. Appl. Sci., 11 (2016) 7059-7067.
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| • |
Alam, S., Kumar, D., Almutairi, B., Bhowmik, P., Goodwin, C. and Parks, G. (2019)
"Small modular reactor core design for civil marine propulsion using micro-heterogeneous duplex fuel. Part I: Assembly-level analysis."
Nucl. Eng. Design, 346 (2019) 157-175.
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| • |
Alberti A., Palmer, T., Ortensi J. and DeHart, M. (2016)
"Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Alcaro, F, Dulla, S. and Ravetto P. (2013)
"Neutronic Evaluations for the EVOL Molten Salt Reactor."
Trans. Am. Nucl. Soc., 108 (2013) 927-930.
|
| • |
Alferov, V., Radaev, A., Shchurovskaya, A., Tikhomirov, G., Hanan, N. and van Heerden, F. (2015)
"Comparative validation of Monte Carlo codes for the conversion of a research reactor."
Ann. Nucl. Energy, 77 (2015) 273-280.
|
| • |
Alhassan, E., Sjöstrand, H., Duan, J., Gustafsson, C., Pomp, S., Österlund, M., Rochman, D. and Koning, A. (2013)
"Uncertainty of lead cross sections on reactor safety for ELECTRA."
In proc. SNA + MC 2013, Paris, France, Oct. 27-31, 2013.
|
| • |
Alhassan, E., Sjöstrand, H., Duan, J., Gustavsson, C., Koning, A., Pomp, S., Rochman, D. and Österlund, M. (2014a)
"Combining Total Monte Carlo and Benchmarks for Nuclear Data Uncertainty Propagation on a Lead Fast Reactor's Safety Parameters."
Nucl. Data Sheets, 118 (2014) 542-544.
|
| • |
Alhassan, E., Sjöstrand, H., Duan, J., Helgesson, P., Pomp, S., Österlund, M., Rochman, D. and Koning, A. (2014b)
"Selecting Benchmarks for Reactor Calculations."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Alhassan, E., Sjöstrand, H., Helgesson, P., Koning, A., Österlund, M., Pomp, S. and Rochman, D. (2015b)
"Uncertainty and correlation analysis of lead nuclear data on reactor parameters for the European Lead Cooled Training Reactor."
Ann. Nucl. Energy, 75 (2015) 26-37.
|
| • |
Alhassan, E., Sjöstrand, H., Helgesson, P., Österlund, M., Pomp, S., Koning, A. and Rochman, D. (2016)
"Selecting benchmarks for reactor simulations: An application to a lead fast reactor."
Ann. Nucl. Energy, 96 (2016) 158-169.
|
| • |
Alhassan, E., Sjöstrand, H., Helgesson, P., Österlund, M., Pomp, S., Koning, A. and Rochman, D. (2016)
"On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology."
Prog. Nucl. Energy, 88 (2016) 43-52.
|
| • |
Allelein, H., Kasselmann, S., Xhonneux, A., Tantillo, F., Trabadela, A. and Lambertz, D. (2016a)
"First results for fluid dynamics, neutronics and fission product behavior in HTR applying the HTR code package (HCP) prototype."
Nucl. Eng. Design, 306 (2016) 145-153.
|
| • |
Allelein, H. and Verfondern, K. (2016b)
"German HTR Phase Out - Experience and Remaining Challenges."
In proc. HTR 2016, Las Vegas, NV, Nov. 6-10, 2016.
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| • |
Allelein, H. and Verfondern, K. (2018)
"Major milestones of HTR development in Germany and still open research issues."
Ann. Nucl. Energy, 116 (2018) 114-127.
|
| • |
Alnoamani, Z., Alameri, S. and Elsawi, M. (2018)
"Neutronic and Fuel Performance Evaluation of Accident Tolerant Fuel Concepts in APR1400 Reactor."
Trans. Am. Nucl. Soc., 118 (2018) 1010-1013.
|
| • |
Altahhan, M., Bhaskar, S., Balestra, P., Hou, J. and Avramova, M. (2018)
"Advanced Liquid Fuel Molten Salt Reactor Core Simulation Using GEN-FOAM."
In proc. ATH 2018, Orlando, Florida, Nov. 11-15, 2018.
|
| • |
Alzaben, Y., Sanchez-Espinoza, V. and Stieglitz, R. (2018a)
"Extending Serpent 2 / SUBCHANFLOW Coupling for Depletion Calculation - Current Status and Challenges."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Alzaben, Y., Ziegahn, C. and Sanchez-Espinoza, V. (2018b)
"Extension of Serpent 2 / SUBCHANFLOW Coupling for Hexagonal Fuel Assemblies."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Alzaben, Y., Sanchez-Espinoza, V. and Stieglitz, R. (2019)
"Core neutronics and safety characteristics of a boron-free core for Small Modular Reactors."
Ann. Nucl. Energy, 132 (2019) 70-81.
|
| • |
Andreades, C., Cisneros, A., Choi, J., Chong, A., Fratoni, M., Hong, S., Huddar, L., Huff, K., Kendrick, J., Krumwiede, D., Laufer, M., Munk, M., Scarlat R. and Zweibau, N. (2016)
"Design Summary of the Mark-I Pebble-Bed, Fluoride Salt-Cooled, High-Temperature Reactor Commercial Power Plan."
Nucl. Technol., 195 (2016) 223-238.
|
| • |
Andrews N., Shirvan K. and Kazimi M. (2013)
"Viability of uranium nitride fueled high-conversion PWR."
Prog. Nucl. Energy,
82 (2015) 28-32.
|
| • |
Antolin, M., Marinho, F., Palma, D. and Martinez, A.
"Spallation Source Modelling for an ADS Using the MCNPX and GEANT4 Packages for Sensitivity Analysis of Reactivity."
Nucl. Data Sheets, 118 (2014) 510-512.
|
| • |
Antolin, M., Martinez, A., Silva Fernando, F. and Palma, D. (2013)
"Calculation of reactivity in subcritical reactors using the method of partial derivatives."
Ann. Nucl. Energy, 60 (2013) 34-38.
|
| • |
Arkoma, A., Huhtanen, R., Leppänen, J., Peltola, J. and Pättikangas, T (2018)
"Calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage."
Ann. Nucl. Energy, 119 (2018) 129-138.
|
| • |
Atkinson, S., Whittle, K., Dean, J. and Abram, T. (2018)
"Prismatic core high temperature reactor fuel modelling incorporating fuel rotation."
Nucl. Eng. Design, 331 (2018) 153-161.
|
| • |
Atkinson, S., Abram, T. J., Litskevich, D. and Merk, B. (2019a)
"Small modular high temperature reactor optimisation – Part 1: A comparison between beryllium oxide and nuclear graphite in a small scale high temperature reactor."
Prog. Nucl. Energy, 111 (2019) 223-232.
|
| • |
Atkinson, S., Litskevich, D. and Merk, B. (2019b)
"Small modular high temperature reactor optimisation part 2: Reactivity control for prismatic core high temperature small modular reactor, including fixed burnable poisons, spectrum hardening and control rods."
Prog. Nucl. Energy, 111 (2019) 233-242.
|
| • |
Aufiero, M., Cammi, A., Fiorina, C., Luzzi, L. and Sartori, A. (2013b)
"A multi-physics time-dependent model for the lead fast reactor single-channel analysis."
Nucl. Eng. Design, 256 (2013) 14-27.
|
| • |
Aufiero, M., Cammi, A., Geoffroy, O., Losa, M., Luzzi, L., Ricotti, M. and Rouch, H. (2014a)
"Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis."
Chem. Eng. Sci. 111 (2014) 390-401.
|
| • |
Aufiero, M., Fiorina, C., Laureau, A., Rubiolo, P. and Valtavirta, V. (2015)
"Serpent-OpenFOAM Coupling in Transient Mode: Simulation of a Godiva Prompt Critical Burst."
In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
|
| • |
Aufiero, M. and Fratoni, M. (2016a)
"Development of Multiphysics Tools for Fluoride-cooled High-temperature Reactors."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Aufiero, M., Martin, M., Fratoni, M., Fridman, E. and Lorenzi, S. (2016b)
"Analysis of the Coolant Density Reactivity Coefficient in LFRs and SFRs via Monte Carlo Perturbation/Sensitivity."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Aufiero, M., Martin, M. and Fratoni, M. (2016c)
"Nuclear Data Uncertainty Quantification for Adjoint–Weighted Quantities via XGPT in Monte Carlo Codes."
Trans. Am. Nucl. Soc., 113 (2016) 429-432.
|
| • |
Aufiero, M. and Fratoni, M. (2017c)
"Stabilization and convergence acceleration in coupled Monte Carlo–CFD calculations: the Newton method via Monte Carlo Perturbation Theory."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Aufiero, M. and Fratoni, M. (2017d)
"A "Discretization-Free" Fission Matrix Approach: the Galerkin Method on the Continuous Fission Kernel."
Trans. Am. Nucl. Soc., 117 (2017) 1444-1447.
|
| • |
Aures, A., Bostelmann, F., Hannstein, V., Velkov, K., Zwermann, W., Guilliard, N., Lapins, J. and Bernnat, W. (2015)
"Depletion Calculation and Uncertainty / Sensitivity Analysis for a Sodium-cooled Fast Spectrum Fuel Assembly."
In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
|
| • |
Aures, A., Pautz, A., Velkov, K. and Zwermann, W. (2017)
"Introduction of a Hybrid Deterministic / Stochastic Calculation Model for Transient Analysis."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Baier, S., Fridman, E., Kliem, S. and Rohde, U. (2014)
"Extension and application of the reactor dynamics code DYN3D for Block-type High Temperature Reactors."
Nucl. Eng. Design, 271 (2014) 431-436.
|
| • |
Baiocco, G., Petruzzi, A. and Aufiero, M. (2017a)
"Uncertainty Quantification Using SCALE 6.2 And GPT Techniques Implemented In Serpent."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Baiocco G. and Petruzzi, A. (2017b)
"PWR Core Analysis Using Helios, Serpent and PARCS Codes."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Baiocco, G., Petruzzi, A., Bznuni, S. and Kozlowski, T. (2017c)
"Analysis of a small PWR core with the PARCS/Helios and PARCS/Serpent code systems."
Ann. Nucl. Energy, 107 (2017) 42-48.
|
| • |
Baker, B., Ortensi, J. and DeHart, M. (2018)
"Modeling of the TREAT M8 Calibration Series Measurements using MAMMOTH."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Baldova, D. and Fridman, E. (2012)
"High conversion Th-U233 fuel assembly for current generation of PWRs."
In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
|
| • |
Baldova, D., Fridman, E. and Shwageraus, E. (2014)
"High conversion Th-U233 fuel for current generation of PWRs: Part I – Assembly level analysis."
Ann. Nucl. Energy, 73 (2014) 552-559.
|
| • |
Batki, B., Kereszturi, A. and Panka, I. (2018)
"Calculation of core safety parameters and uncertainty analyses during unprotected transients for the ALLEGRO and a sodium-cooled fast reactor."
Ann. Nucl. Energy, 118 (2018) 260-271.
|
| • |
Bennett, A., Martin, N. and Schneider, M. (2019a)
"Validation of APOLLO2-A Against SERPENT2 on BWR Lattices."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
|
| • |
Bennett, A., Bache, G., Martin, N. and Senecal, J. (2019b)
"BWR Spacer Grid Modeling Using SERPENT 2 / STAR-CCM+ Coupling."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
|
| • |
Bernt, N., Lange, C., Viebach, M., Hennig, D. and Hurtado, A. (2018)
"The Influence of Full-Core Deflection to the Nodalized Cross Sections."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Bess, J. Dusanter, L., Woolstenhulme, N., Parry, J., Hill, C. and Davisa, C. (2018)
"Core Power Flattening Studies Supporting Narrowing Transient Pulse Widths in TREAT."
Trans. Am. Nucl. Soc., 118 (2018) 997-1000.
|
| • |
Bilodid, Y., Fridman, E., Margulis, M., Kotlyar, D. and Shwageraus, E. (2014)
"Verification of the Spectral History Correction Method with Fully Coupled Monte Carlo Code BGCore."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Bilodid, Y., Kotlyar, D., Margulis, M., Fridman, E. and Shwageraus. E. (2015)
"Spectral history model in DYN3D: Verification against coupled Monte-Carlo thermal-hydraulic code BGCore."
Ann. Nucl. Energy, 81 (2015) 34–40.
|
| • |
Bilodid, Y., Kotlyar, D., Shwageraus. E., Fridman, E. and Kliem, S. (2016)
"Hybrid microscopic depletion model in nodal code DYN3D."
Ann. Nucl. Energy, 92 (2016) 397-406.
|
| • |
Bilodid, Y., Fridman, E., Kliem, S., Kotlyar, D. and Shwageraus, E. (2016)
"Microscopic Depletion with the Correction of Microscopic Cross Sections in Nodal Diffusion Code DYN3D."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Bilodid, Y., Fridman, E., Kotlyar, D. and Shwageraus, E. (2017)
"Explicit decay heat calculation in the nodal diffusion code DYN3D."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Bilodid, Y. and Fridman, E. (2018)
"Serpent Solution of the X2 VVER-1000 Benchmark Fresh Core Experiments."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Bilodid, Y., Grundmann, U. and Kliem, S. (2018)
"The HEXNEM3 nodal flux expansion method for the hexagonal geometry in the code DYN3D."
Ann. Nucl. Energy, 116 (2018) 187-194.
|
| • |
Björk, K. and Fredriksson, P. (2014)
"Development of a Fuel Performance Code for Thorium-Plutonium Fuel."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Björk, K. and Kekkonen, L. (2015)
"Thermal–mechanical performance modeling of thorium–plutonium oxide fuel and comparison with on-line irradiation data."
J. Nucl. Mat., 467 (2015) 876-885.
|
| • |
Bjök, K. and Netterbrant, C. (2018)
"Thorium as an additive for improved neutronic properties in boiling water reactor fuel."
Ann. Nucl. Energy, 113 (2018) 470-475.
|
| • |
Blaise, P., Laureau, A., Ros, P., Leconte, P. and Routsonis, K. (2019)
"Transient fission matrix approach for assessing complex kinetics behavior in the ZEPHYR ZPR coupled core configurations."
Ann. Nucl. Energy, 128 (2019) 390-397.
|
| • |
Bogetic, S., Greenop, A., Haneklaus, N., Poresky, C. and Shen D. (2016)
"Near-Term Deployment Viability of Liquid-Fuel Molten Salt Reactors."
Trans. Am. Nucl. Soc., 115 (2016) 73-76.
|
| • |
Boschetti F., Villarino, E., Lipiec, W. and Kucukboyaci, V. (2018)
"New Resonance Treatment for PHOENIX5."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Bousquet, J., Seubert, A. and Sarkadi, P. (2018)
"3-D Coupled PARCS/ATHLET Simulation of SFR Using an Explicit Radial Expansion Model."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Bousquet, J., Seubert, A. and Henry, R. (2019)
"3-D Coupled PARCS/ATHLET Transient Simulation of SFR Using Detailed Expansion Modeling."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
|
| • |
Boyarinov, V., Fomichenko P. and Grol, A. (2016)
"Use of Cross-Section Covariance Information in Uncertainty Analysis at Modeling HTGR Neutron Physics."
In proc. HTR 2016, Las Vegas, NV, Nov. 6-10, 2016.
|
| • |
Bortot, S., Wallenius, J., Suvdantsetseg, E. and Pelloni, S. (2013)
"Modeling issues in small HLMC fast reactors: ELECTRA case study."
Trans. Am. Nucl. Soc., 109 (2013) 2261-2264.
|
| • |
Bortot, S., Pelloni, S. and Mikityuk, K. (2014)
"Methodology Assessment for the Evaluation of the Coolant Void Worth in Sodium Fast Reactors With a Low Void Effect Core Design."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Bostelmann, F., Hammer, H., Ortensi, J., Strydom, G., Velkov, K. and Zwermann, W. (2016)
"Criticality calculations of the Very High Temperature Reactor Critical Assembly benchmark with Serpent and SCALE/KENO-VI."
Ann. Nucl. Energy, 90 (2016) 343–352.
|
| • |
Bostelmann, F., Velkov K., Zwermann, W., Hammer, H. and Strydom G. (2016)
"Impact of Nuclear Data Uncertainties on Criticality Calculations of the Very High Temperature Reactor Critical Assembly Benchmark."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Bostelmann, F., Strydom, G., Reitsma, F. and Ivanov, K. (2016)
"The IAEA coordinated research programme on HTGR uncertainty analysis: Phase I status and Ex. I-1 prismatic reference results."
Nucl. Eng. Design, 306 (2016) 77-88.
|
| • |
Bostelmann, F., Brown, N., Pautz, A., Rearden, B., Velkov, K. and Zwermann, W. (2017a)
"SCALE Multi-Group Libraries for Sodium-cooled Fast Reactor Systems."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Bostelmann, F. and Strydom, G. (2017b)
"Nuclear data uncertainty and sensitivity analysis of the VHTRC benchmark using SCALE."
Ann. Nucl. Energy, 110 (2017) 317-329.
|
| • |
Bostelmann, F., Williams, M., Celik, C., Ellis, R., Ilas, G. and Rearden, B. (2018)
"Assessment of SCALE Capabilities for High Temperature Reactor Modeling and Simulation."
Trans. Am. Nucl. Soc., 119 (2018) 1073-1076.
|
| • |
Bousquet, J., Seubert, A., Velkov, K. and Weiß, F. (2016)
"Neutronic Modeling of the MYRRHA Minimum Critical Core with PARCS and Serpent."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Bousquet, J., Bostelmann, F., Velkov, K. and Zwermann, W. (2017)
"Macroscopic Cross Section Generation with SCALE 6.2 for the MYRRHA Minimal Critical Core."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Brankov, V., Khvostov, G., Mikityuk, K., Pautz, A., Restani, R., Abolhassani, S., Ledergerber, G. and Wiesenack, W. (2016)
"Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels."
Nucl. Eng. Design, 305 (2016) 559-568.
|
| • |
Brown, N., Ludewig, H., Aronson, A., Raitses, G. and Todosow, M. (2013a)
"Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients."
Ann. Nucl. Energy, 62 (2013) 538-547.
|
| • |
Brown, N., Ludewig, H., Aronson, A., Raitses, G. and Todosow, M. (2013b)
"Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback."
Ann. Nucl. Energy, 62 (2013) 548-557.
|
| • |
Brown, N., Aronson, A., Todosow, M., Brito, R. and McClellan, K. (2014a)
"Neutronic performance of uranium nitride composite fuels in a PWR."
Nucl. Eng. Design, 275 (2014) 393–407.
|
| • |
Brown, N., Aronson, A. and Todsow, M. (2014b)
"BNL Metal Fuel Lattice Experiments: Candidates for Reactor Physics Benchmark Evaluation."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Brown, N., Raitses, G. and Todsow, M. (2014c)
"Fuel Cycle Analysis of Self-Sustaining Water Cooled Reactors with 232Th/233U Fuel and Impact of 233U (n,g) Cross Section Evaluations."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Brown, N., Todsow, M. and McClellan, K. (2014d)
"Uranium nitride composite fuels in a pressurized water reactor: exploration of multi-batch cycle length and UB4 admixture for reactivity control."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Brown, N., Todosow, M. and Cuadra, A. (2015a)
"Screening of advanced cladding materials and UN–U3Si5 fuel."
J. Nucl. Mat., 462 (2015) 26-42.
|
| • |
Brown, N., Powers, J., Feng, B., Heidet, F., Stauff, N., Zhang, G., Todosow, M., Worrall, A., Gehin, J., Kim, T. and Taiwo, A. (2015b)
"Sustainable thorium nuclear fuel cycles: A comparison of intermediate and fast neutron spectrum systems."
Nucl. Eng. Design, 289 (2015) 252–265.
|
| • |
Brown, N., Worral, A. and Todosow, M. (2017a)
"Impact of thermal spectrum small modular reactors on performance of once-through nuclear fuel cycles with low-enriched uranium."
Ann. Nucl. Energy, 101 (2017) 166-173.
|
| • |
Brown, N., Betzler, B., Carbajo, J., Wysocki, A., Greenwood M., Gentry, C. and Qualls, A. (2017b)
"Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis."
Ann. Nucl. Energy, 103 (2017) 49-59.
|
| • |
Buiron, L., Rimpault, G., Fontaine, B., Kim, T., Stauff, N., Taiwo, T., Yamaji, A., Gulliford, J., Fridmann, E., Pataki, I., Keresztúri, A., Tóta, Á. Kugo, K., Sugino, K., Uematsu, M., Lin Tan, R., Kozlowski, T., Parisi, C. and Ponomarev, A. (2014)
"Evaluation if Large 3600 MWth Sodium-Cooled Fast Reactor OECD Neutronic Benchmarks."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Cai, L., Pénéliau, Y., Tommasi, J., Vidal, J. and Diop, C. (2014)
"Leakage-corrected fast reactor assembly calculation with Monte-Carlo code TRIPOLI4 and its validation methodology."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Ćalić, D., Trkov, A. and Kromar, M. (2012a)
"Neutron multigroup homogenized cross section determination with the Monte Carlo method."
In proc. 21st International Conference Nuclear Energy for New Europe 2012, Ljubljana, Slovenia, Sept. 5-7, 2012.
|
| • |
Ćalić, D., Trkov, A. and Kromar, M. (2012b)
"Parallelisation of burnup calculations performed with Monte Carlo code Serpent."
In proc. 21st International Conference Nuclear Energy for New Europe 2012, Ljubljana, Slovenia, Sept. 5-7, 2012.
|
| • |
Ćalić, D., Kromar, M. and Trkov, A. (2014)
"Effective Diffusion Homogenization of Cross Sections With the Monte Carlo Method."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Ćalić, D., Trkov, A., Kromar, M. and Snoj, L. (2016a)
"Use of Effective Diffusion Homogenization method with the Monte Carlo code for light water reactor."
Ann. Nucl. Energy, 94 (2016) 392-398.
|
| • |
Ćalić, D. and Trkov, A. (2016b)
"Monte Carlo Simulation on Krško NPP."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Ćalić, D., Zerovnik, G., Trkov, A. and Snoj, L. (2016c)
"Validation of the Serpent 2 code on TRIGA Mark II benchmark experiments."
Appl. Radiat. Isot., 107 (2016) 165-170.
|
| • |
Ćalić, D., Stancar, Z. and Snoj, L. (2018)
"Analysis of VENUS-2 benchmark using Serpent 2 code."
Ann. Nucl. Energy, 116 (2018) 334-346.
|
| • |
Ćajko, F., Sećansky, M., Chrebet, T., Zajac, R. and Darilek, P. (2016)
"Neutronic analysis of absorbing materials for the control rod system in reactor ALLEGRO."
Kerntechnik, 81 (2016) 445-451.
|
| • |
Canbakan, A., Hébert, A. and Vidal, J. (2015)
"Accuracy of a Subgroup Method for Pressurized Water Reactor Fuel Assembly Models."
In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
|
| • |
Canepa, S., Hursin, M., Ferroukhi, H. and Pautz, A. (2013)
"Preparation of nuclear libraries with deterministic and stochastic methods for for LWR reflectors."
In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
|
| • |
Cao, Y., Gohar, Y. and Kraus, A. (2018)
"Accelerator-Driven Subcritical System Analysis for Utilizing the Minor Actinides of the U.S. Spent Nuclear Fuel Inventory."
Trans. Am. Nucl. Soc., 119 (2018) 15-19.
|
| • |
Castagna, C., Chiesa D., Cammi A., Boarin S., Previtali E., Sisti M., Nastasi M., Salvini A., Magrotti G. and Prata, M. (2018a)
"A new model with Serpent for the first criticality benchmarks of the TRIGA Mark II reactor."
Ann. Nucl. Energy, 113 (2018) 171-176.
|
| • |
Castagna, C., Cervi, E., Lorenzi, S., Cammi, A., Chiesa, D., Nastasi, M., Sisti, M. and Previtali, E. (2018b)
"Effects of a Multi-physics Coupling Approach in Monte Carlo Burnup Calculations."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Cervi, E., Lorenzi, S., Cammi, A. and Luzzi, L. (2018)
"Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Cervi, E. Cammi, A. and Zio, E. (2019a)
"A new approach for nuclear reactor analysis based on complex network theory."
Prog. Nucl. Energy, 112 (2019) 96-106.
|
| • |
Cervi, E., Lorenzi, S., Cammi, A. and Luzzi, L. (2019b)
"Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor."
Chem. Eng. Sci. 193 (2019) 379-393.
|
| • |
Cervi, E., Lorenzi, S., Luzzi, L. and Cammi, A. (2019c)
"Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches."
Ann. Nucl. Energy, 132 (2019) 227-235.
|
| • |
Cervi, E., Cammi, A. and Zio, E. (2019d)
"A new approach for nuclear reactor analysis based on complex network theory."
Prog. Nucl. Energy, 112 (2019) 96-106.
|
| • |
Cervi, E., Lorenzi, S., Cammi, A. and Luzzi, L. (2019e)
"Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor."
Nucl. Eng. Design, 346 (2019) 209-219.
|
| • |
Cheng, Y. and Roberts, J. (2016)
"Impact of Spatial Discretization on Reactivity Biases in Depleted TRIGA Fuel."
Trans. Am. Nucl. Soc., 115 (2016) 1160-1162.
|
| • |
Cheng, Y. and Roberts, J. (2017)
"A study of reactivity biases and their dependence on spatial discretization in depleted TRIGA fuel."
Ann. Nucl. Energy, 108 (2017) 126-131.
|
| • |
Chersola, D., Lomonaco, G., Marotta, R. and Mazzini, G. (2014a)
"Comparison between SERPENT and MONTEBURNS codes applied to burnup calculations of a GFR-like configuration."
Nucl. Eng. Design, 273 (2014) 542–554.
|
| • |
Chersola, D., Lomonaco, G., and Mazzini, G. (2014b)
"Cross sections influence on Monte Carlo based burnup codes."
In proc. ICONE22, Prague, Czech Republic, Jul. 7-11, 2014.
|
| • |
Chersola, D., Lomonaco, G. and Mazzini, G. (2015)
"Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration."
ASME J. of Nuclear Rad Sci., 1 (2015) 031004.
|
| • |
Chersola, D., Mazzini, G., Kostál, M., Miglierini, B., Hrehor, M., Lomonaco, G., Borreani, W. and Ruscák, M. (2016)
"Application of Serpent 2 and MCNP6 to study different criticality configurations of a VVER-1000 mock-up."
Ann. Nucl. Energy, 94 (2016) 109-122.
|
| • |
Colak, U. and Turkmen, M. (2011)
"The Effect of Neutron Energy Spectrum on Actinide Management in High Temperature Reactors."
In proc. 20th International Conference Nuclear Energy for New Europe 2011, Bovec, Slovenia, Sept. 12-15, 2011.
|
| • |
Colling, B., Burns, A., Eade, T. and Leppänen, J. (2018)
"Assessment of Serpent 2 application to fusion neutronics."
In proc. 30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Italy, Sept. 16-21, 2018.
|
| • |
Cosgrove, P. and Shwageraus, E. (2017)
"Development of MoCha-Foam: a new Method of Characteristics Neutron Transport Solver for OpenFOAM."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Cosgrove, P. Shwageraus, E. and Parks, G. (2018)
"Perturbation-Based Coupling of Monte Carlo with Depletion for Multiple Burnable Regions."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Cosgrove, P., Shwageraus, E., Parks, G. (2019)
"Stability Diagnosis of High-Fidelity Transport-Depletion Problems with Monte Carlo Perturbation Theory."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
|
| • |
Daeubler, M., Jimenez, J. and Sanchez, V. (2014a)
"Generation and Application of Interface Discontinuity Factors in the Reactor Simulator DYN3D."
In proc. ICAPP 2014, Charlotte, NC, Apr. 6-9, 2014.
|
| • |
Daeubler, M., Jimenez, J. and Sanchez, V. (2014b)
"Development of a High-Fidelity Monte Carlo Thermal-Hydraulics Coupled Code System Serpent/SUBCHANFLOW -- First Results."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Daeubler, M., Ivanov, A., Sjenitzer, B., Sanchez, V., Stieglitz, R. and Macian-Juan, R. (2015)
"High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW."
Ann. Nucl. Energy, 83 (2015) 325-375.
|
| • |
Davies, U., Shwageraus, E. and Lau, C. (2018)
"Uncertainty & Sensitivity Analysis of Th-MOX Fuel in ABWRs."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Davies, U., Lindley, B., Tollit, B and Shwageraus, E. (2019)
"Whole-Core Validation of the Superphénix Reactor Using WIMS11 and an Investigation into a Hybrid RZ-HEX SP3 Calculation Route."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
|
| • |
da Cruz, D. (2016)
"Uncertainty due to Nuclear Data for an MTR Fuel Assembly."
Trans. Am. Nucl. Soc., 115 (2016) 1357-1359.
|
| • |
Darnowski, P., Potapczyk, K., Gatowski, M. and Niewinsk, G. (2016)
"Development of one-way-coupling methodology between severe accident integral code MELCOR and Monte Carlo neutron transport code SERPENT."
Procedia Engineering, 157 (2016) 207-213.
|
| • |
Darnowski, P., Potapczyk, K. and Swirski, K. (2017)
"Investigation of the recriticality potential during reflooding phase of Fukushima Daiichi Unit-3 accident."
Ann. Nucl. Energy, 99 (2017) 495-509.
|
| • |
Darnowski, P., Ignaczak, P., Obrebski, P., Stepien, M. and Niewinski, G. (2018a)
"Simulations of the AP1000-based reactor core with serpent computer code."
Archive of Mechanical Engineering, 65 (2018) 295-325.
|
| • |
Darnowski, P. and Mikolajczak, A. (2018b)
"Monte Carlo Simulations of the 1000 MWth SFR OECD/NEA Benchmark with SERPENT Code."
In proc. 16TH INTERNATIONAL CONFERENCE OF NUMERICAL ANALYSIS AND APPLIED MATHEMATICS, Rhodes, Greece, Sept 13-18, 2018.
|
| • |
Davidson, G., Pandy, T., Isotalo, A., Johnson, S., Evans, T. and Wieselquist, W. (2016)
"Nuclide Depletion Capabilities in the SHIFT Monte Carlo Code."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Davidson, G., Pandya, T., Johnson, S., Evans, T., Isotalo, A., Gentry, C. and Wieselquist, W. (2018)
"Nuclide depletion capabilities in the Shift Monte Carlo code."
Ann. Nucl. Energy, 114 (2018) 259-276.
|
| • |
del-Valle-Gallegos, E., Lopez-Solis, R., Arriaga-Ramirez, L., Gomez-Torres, A. and Puente-Espel, F (2018)
"Verification of the multi-group diffusion code AZNHEX using the OECD/NEA UAM Sodium Fast Reactor Benchmark."
Ann. Nucl. Energy, 114 (2018) 592-602.
|
| • |
DeHart, M. and Bowman, S. (2011)
"Reactor Physics Methods and Analysis Capabilities in SCALE."
Nucl. Sci. Eng., 174 (2011) 196-213.
|
| • |
DeHart, M., Goluoglu, S. and Leppänen, J. (2009)
"A Comparison of Deterministic and Monte Carlo Depletion Methods for HTGR Fuel Elements."
Trans. Am. Nucl. Soc., 101 (2009) 778-781.
|
| • |
DeHart, M., Pope, M., Nigg, D., Jamison, R. and Morrell, S. (2013)
"Fuel element design and analysis for Advanced Test Reactor conversion to LEU fuel."
Trans. Am. Nucl. Soc., 109 (2013) 1343-1347.
|
| • |
DeHart, M., Ortensi, J., Baker, B., Gleicher, F., Wang, Y. and Schunert, S. (2016)
"Research in Support of TREAT Kinetics Calculations Using RattleSNake/Bison Coupling Within MAMMOTH."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
DeHart, M. Baker, B. and Orentsi, J. (2017a)
"Interpretation of energy deposition data from historical operation of the transient test facility (TREAT)."
Nucl. Eng. Design, 322 (2017) 504-521.
|
| • |
DeHart, M., Baker B. and Ortensi, J. (2017b)
"Assessment of Uncertainties in Energy Deposition Data for the Transient Test Facility (TREAT)."
Trans. Am. Nucl. Soc., 117 (2017) 799-803.
|
| • |
DeHart, M., Karriem, Z., Pope, M. and Johnson, M. (2018a)
"Fuel element design and analysis for potential LEU conversion of the Advanced Test Reactor."
Prog. Nucl. Energy, 104 (2018) 117-135.
|
| • |
DeHart, M., Karriem Z. and Pope, M. (2018b)
"Evaluation of the Enhanced LEU Fuel (ELF) Design for Conversion of the Advanced Test Reactor to a Low-Enrichment Fuel Cycle."
Nucl. Technol., 201 (2018) 247-266.
|
| • |
Demazière, C. (2016)
"Investigation of the Bias Coming From Spectrum Corrections in the Simulations of Nuclear Reactor Transients."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Denig A., Ahmed R., Gates J.T., Mehta V. and Kotlyar D. (2018)
"Decay Heat Calculations and Propellant Requirements for a Low-enriched Cermet-Based Nuclear Therma Propulsion Engine."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
de Stefani, G., Moreira, J., Maiorino, J. and Rossi, P. (2019)
"Detailed neutronic calculations of the AP1000 reactor core with the Serpent code."
Prog. Nucl. Energy, 116 (2019) 95-107.
|
| • |
Dicuonzo, O., Fabrizio, V., Caron, D., Dulla, S., Carta, M. and Ravetto, P. (2017)
"Computational Analysis of TAPIRO Experiments by the SERPENT and ERANOS Codes."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Di Gesare, C., Caron, D., Dulla, S., Ravetto, P., Carta, M. and Fabrizio, V. (2018)
"Use of new Nuclear Data Libraries for the Monte Carlo Analysis of Neutronic Measurements in the Tapiro Reactor."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Dion, M. and Marleau, G. (2016)
"Sensitivity of Cross Sections to Isotopic Densities for Subgroup Resonance Self-Shielding Calculations."
Nucl. Technol., 183 (2016) 261-274.
|
| • |
Do, M., Nguyen, X. and Kim, Y. (2018)
"Feasibility of a Very-Low-Boron Core Design For APR1400 with 24-Month Cycle Length."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Duerigen, S. and Fridman, E. (2012)
"The simplified P3 approach on a trigonal geometry of the nodal reactor code DYN3D."
Kerntechnik, 77 (2012) 226-229.
|
| • |
Dufek, J., Kotlyar, D., Shwageraus, E. and Leppänen, J. (2013b)
"Numerical stability of the predictor-corrector method in Monte Carlo burnup calculations of critical reactors."
Ann. Nucl. Energy, 56 (2013) 34-38.
|
| • |
Dulla, S., Nervo, M., Ravetto, P. and Carta, M. (2013)
"Spatial and Spectral Effects in Subcritical System Pulsed Experiments."
In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
|
| • |
Dupont, M., Eklund, M., Caracappa, P. and Ji, W. (2019)
"Development of critical experiments to provide validation data for multiphysics coupling codes."
Ann. Nucl. Energy, 128 (2019) 256-267.
|
| • |
Dupont, M., Eklund, M., Caracappa, P. and Ji, W. (2020)
"Experimental measurements of isothermal reactivity coefficient and temperature-dependent reactivity changes with associated uncertainty evaluations."
Prog. Nucl. Energy, 118 (2020) 103131.
|
| • |
Dyrda, J., Hill, I., Fiorito, L., Cabellos, O., Soppera, N. (2018)
"A comparison of uncertainty propagation techniques using NDaST: full, half or zero Monte Carlo?."
EPJ Nuclear Sci. Technol., 4 (2018) Article 14.
|
| • |
Eades, M. and Venneri, P. (2016)
"Xenon-135m in Nuclear Thermal Propulsion."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Eades, M., Chaleff, E., Venneri, P. and Blue, T. (2017)
"The influence of Xe-135m on steady-state xenon worth in thermal molten salt reactors."
Prog. Nucl. Energy, 93 (2016) 397-405.
|
| • |
Eklund, M., Dupont, M., Caracappa P. and Ji, W. (2017)
"Neutronics Simulations of the RPI Walthousen Reactor Critical Facility (RCF) Using Proteus-SN."
Trans. Am. Nucl. Soc., 117 (2017) 114-115.
|
| • |
Eklund, M., Dupont, M., Caracappa, P., Ji, W. and Mahadevan, V. (2018)
"Neutronics Modeling and Simulation of Temperature-dependent Experiments Performed at the Walthousen Reactor Critical Facility (RCF) Using Proteus-SN."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Elsawi, M. and Alnoamani, Z. (2016)
"Neutronic Analysis of the APR1400 Reactor Core with SCALE and Serpent Reactor Physics Codes - Power Distribution."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Elter, Z., Caldeira Balkeståhl, L., Grape, S. and Hellesen, C. (2018)
"Partial Defect Identification in PWR Spent Fuel Using Passive Gamma Spectroscopy."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Elzohery, R., Abdo, M. and Roberts, J. (2018)
"Comparison Between Gaussian Processes and DMD Surrogates for Isotopic Composition Prediction."
Trans. Am. Nucl. Soc., 118 (2018) 459-462.
|
| • |
Evitts, L., Gilbert, M., Middleburgh, S., Lee, B. and Dahlfors, M. (2021)
"Utilizing neutronics modelling to predict changing Pu ratios in UO2 in the presence of Th."
Prog. Nucl. Energy, 137 (2021) 103762.
|
| • |
Faure, B. and Marleau, G. (2017)
"Simulation of a sodium fast core: Effect of B1 leakage models on group constant generation."
Ann. Nucl. Energy, 99 (2017) 484-494.
|
| • |
Fei, T., Vezzoni, B., Marchetti, M., van Rooijen, W. and Zhang Y. (2016)
"Neutronics Benchmark for EBR-II Shutdown Heat Removal Test SHRT-45R."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Fejt, F. (2015)
"CUDA-Accelerated Algorithm in 3D Neutron Diffusion Calculation at the VR-1."
Trans. Am. Nucl. Soc., 113 (2015) 1602-1605.
|
| • |
Fejt, F. and Frybort, J. (2018)
"Analysis of a small-scale reactor core with PARCS/Serpent."
Ann. Nucl. Energy, 117 (2018) 25-31.
|
| • |
Fejt, F., Sevecek, M., Frybort, J. and Novak, O. (2019)
"Study on neutronics of VVER-1200 with accident tolerant fuel cladding."
Ann. Nucl. Energy, 124 (2019) 579-591.
|
| • |
Ferraro, D. and Villarino, E. (2011a)
"Calculations for a BWR lattice with adjacent gadolinium pins using the Monte Carlo cell code Serpent v.1.1.7."
Sci. Technol. Nucl. Install., 2011 (2011), Article ID 659406.
|
| • |
Ferraro, D. and Villarino, E. (2011b)
"OPAL reactor calculations using the Monte Carlo code Serpent."
In proc. 4th International Symposium on Material Testing Reactors,
Oarai, Japan, Dec. 5-9, 2011.
|
| • |
Ferraro, D., Cuello E. and Sardella, F. (2013)
"Low Power Research Reactor Calculations using Deterministic and Stochastical Transport Codes."
In proc. 6th International Symposium on Material Testing Reactors (ISMTR),
Bariloche, Argentina, Oct. 28-31, 2013.
|
| • |
Ferraro, D., Villarino, E. (2014)
"OPAL Reactor Full 3-D Calculations using the Monte Carlo Code Serpent 2."
In proc. 16th International Group on Research Reactor (IGORR),
Bariloche, Argentina, Nov. 17-21, 2014.
|
| • |
Ferraro, D., Villarino, E. (2016)
"Full 3-D core calculations with refueling for the OPAL Research Reactor using Monte Carlo Code Serpent 2."
Ann. Nucl. Energy, 92 (2016) 369-377.
|
| • |
Ferraro D., Alberto P., Villarino E. and Doval A. (2018)
"A Multi-physics Analysis for the actuation of the SSS in OPAL Reactor."
EPJ Nuclear Sci. Technol., 4 (2018) Article 8.
|
| • |
Ferraro, D., Garcia, M., Mercatali, L., Sanchez, V., Leppänen, J. and Valtavirta, V. (2018)
"Foreseen Capabilities, Bottlenecks Identification and Potential Limitations of Serpent MC Transport Code in Large-Scale Full 3-D Burnup Calculations."
In proc. ICONE26, London, UK, Jul. 22-26, 2018.
|
| • |
Ferraro, D., Garcia, M., Imke, U., Valtavirta, V., Leppänen, J. and Sanchez-Espinoza, V. (2019a)
"Serpent/SCF pin-level multiphysics solutions for the VERA Fuel Assembly benchmark."
Ann. Nucl. Energy, 128 (2019) 102-114.
|
| • |
Ferraro, D., Faucher, M., Mancusi, D., Zoia, A., Valtavirta, V., Leppänen, J. and Sanchez-Espinoza, V. (2019b)
"SERPENT and TRIPOLI4® Transient Calculations Comparisons for SEVEral Reactivity Insertion Scenarios in a 3D PWR Minicore Benchmark."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
|
| • |
Ferraro, D., Garcia, M., Valtavirta, V., Imke, U., Tuominen, R., Leppänen, J. and Sanchez-Espinoza, V. (2020a)
"Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for the SPERT-IIIE hot full power tests."
Ann. Nucl. Energy, 142 (2020) 10387.
|
| • |
Ferraro, D., Garcia, M., Valtavirta, V., Imke, U., Tuominen, R., Leppänen, J. and Sanchez-Espinoza, V. (2020b)
"Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for a PWR minicore."
Ann. Nucl. Energy, 137 (2020) 107090.
|
| • |
Fiorina, C., Aufiero, M., Cammi, A., Franceschini, F., Krepel, J., Luzzi, L., Mikityuk, K. and Ricotti, M. E. (2013)
"Investigation of the MSFR core physics and fuel cycle characteristics."
Prog. Nucl. Energy, 68 (2013) 153-168.
|
| • |
Fiorina, C., Lathouwers, D., Aufiero, M., Cammi, A., Guerrieri, C., Kloosterman, J. L., Luzzi, L. and Ricotti, M. E (2014)
"Modelling and analysis of the MSFR transient behaviour."
Ann. Nucl. Energy, 64 (2014) 485-498.
|
| • |
Fiorina, C., Mikityuk, K. and Pautz, A. (2015)
"GeN-Foam: A Novel Multi-Physics Solver for Reactor Analysis – Status and Ongoing Developments."
Trans. Am. Nucl. Soc., 113 (2015) 1132-1134.
|
| • |
Fiorina, C., Clifford, I., Aufiero, M., Mikityuk, K. (2015)
"GeN-Foam: a novel OpenFOAM based multi-physics solver for 2D/3D transient analysis of nuclear reactors."
Nucl. Eng. Design, 294 (2015) 24-37.
|
| • |
Fiorina, C. and Pautz, A. (2016)
"Status and Ongoing Developments for the GeN-Foam Multi-Physics Solver."
Trans. Am. Nucl. Soc., 115 (2016) 1106-1109.
|
| • |
Fiorina, C., Hursin, M. and Pautz, A. (2017)
"Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor."
Ann. Nucl. Energy, 101 (2017) 419-428.
|
| • |
Fiorina, C., Radman, S., Koc, M., and Pautz, A. (2019a)
"Detailed Modelling of the Expansion Reactivity Feedback in Fast Reactors Using OpenFOAM."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
|
| • |
Fiorina, C. (2019b)
"Impact of the volume heat source on the RANS-based CFD analysis of Molten Salt Reactors."
Ann. Nucl. Energy, 134 (2019) 376-382.
|
| • |
Floyd, D., Ridley, G., Tidwell, P. and Tebbs, W. (2018)
"Concept Reactor for Extraterrestrial Surface Power: PULSR."
Trans. Am. Nucl. Soc., 119 (2018) 62-65.
|
| • |
Franceschini, F., Salazar, D., Ouisloumen, M., Godfrey, A., Stimpson, S., Collins, B. and Gentry, C. (2016)
"AP1000 PWR Cycle 1 HFP Depletion Simulations with VERA-CS."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Fratoni, M. and Terrani, K. (2012)
"Metal Matrix Microencapsulated (M3) fuel neutronics performance in PWRs."
Trans. Am. Nucl. Soc., 107 (2012) 1025-1028.
|
| • |
Fratoni, M. and Terrani, K. (2012)
"PWR core design with Metal Matrix Micro-encapsulated (M3) fuel."
Prog. Nucl. Energy, 100 (2017) 419-426.
|
| • |
Fridman, E. and Shwageraus, E. (2012b)
"Demonstration of the Serpent Monte-Carlo Code Applicability to Few-Group Constants Generation for Existing and Advanced Reactor Concepts."
In proc. 26th Conference of the Nuclear Societies in Israel, Dead Sea, Israel, Feb. 21-23, 2012.
|
| • |
Fridman, E. and Shwageraus, E. (2013a)
"Modeling of SFR cores with Serpent-DYN3D codes sequence."
Ann. Nucl. Energy, 53 (2013) 354-363.
|
| • |
Fridman, E., Duerigen, S., Bilodid, Y., Kotlyar, D. and Shwageraus, E. (2013b)
"Axial discontinuity factors for the nodal diffusion analysis of high conversion BWR cores."
Ann. Nucl. Energy, 62 (2013) 129-136.
|
| • |
Fridman, E., Leppänen, J. and Wemple, C. (2013c)
"Comparison of Serpent and HELIOS-2 as applied for the PWR few-group cross section generation."
In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
|
| • |
Fridman, E., Rachamin, R. and Shwageraus, E. (2013d)
"Generation of SFR few-group constants using the Monte Carlo code Serpent."
In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
|
| • |
Fridman, E. (2013e)
"Serpent Monte-Carlo-Code: An Advanced Tool for Few-Group Cross Section Generation."
ATW, 58 (2013) 156-157.
|
| • |
Fridman, E., Kochetkov A. and Krása, A. (2017)
"Modeling of FREYA fast critical experiments with the Serpent Monte Carlo code."
Ann. Nucl. Energy, 108 (2017) 239-252.
|
| • |
Frybort, J. and Vocka, R. (2017)
"Macroscopic Data Generation for Full-Core VVER Reactor Calculations by Serpent."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Galchenko, V., Gulik, V. and Shlapak, I. (2016)
"Using of the Serpent code based on the Monte-Carlo method for calculation of the VVER-1000 fuel assembly characteristics."
Nuclear Physics and Atomic Energy, 3 (2016) 250-258. (in Ukranian)
|
| • |
Galicia-Aragón, J., Francois, G., Bastida-Ortiz, G., Martín-del-Campo, C., Vallejo-Quintero, J. and del-Valle-Gallegos, E. (2018)
"Initial verification of AZNHEX hexagonal-z neutron diffusion code with MCNP6 for two different study cases."
Prog. Nucl. Energy, 106 (2018) 284-292.
|
| • |
Gamarino, M., Dall’Osso, A., Lathouwers D. and Kloosterman, J. (2017)
"Spectral Rehomogenization of Nodal Cross-Sections via Proper Orthogonal Decomposition."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Gamarino, M., Dall'Osso, A., Lathouwers, D. and Kloosterman, J. (2018a)
"A neutron-leakage spectrum model for on-the-fly rehomogenization of nodal cross sections."
Ann. Nucl. Energy, 116 (2018) 257-279.
|
| • |
Gamarino, M., Dall’Osso, A., Lathouwers D. and Leen Kloosterman, J. (2018b)
"Rehomogenization of Nodal Cross Sections via Modal Synthesis of Neutron Spectrum Changes."
Nucl. Sci. Eng., 190 (2018) 1-30.
|
| • |
Garcia, M., Ferraro, D., Sanchez, V., Mercatali, L., Leppänen, J. and Valtavirta, V. (2018)
"Development of a Spatial Domain Decomposition Scheme for Monte Carlo Neutron Transport."
In proc. ICONE26, London, UK, Jul. 22-26, 2018.
|
| • |
Garcia, M., Ferraro, D., Valtavirta, V., Imke, U., Tuominen, R., Sanchez-Espinoza, V. and Mercatali, L. (2019)
"Development of an Object-Oriented Serpent2-SUBCHANFLOW Coupling and Verification with Problem 6 of the VERA Core Physics Benchmark."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
|
| • |
Garcia, M., Tuominen, R., Gommlich, A., Ferraro, D., Valtavirta, V., Imke, U., Van Uffelen, P., Mergatali, L., Sanches-Espinoza, V., Leppänen, J. and Kliem, S. (2020a)
"A Serpent2-SUBCHANFLOW-TRANSURANUS coupling for pin-by-pin depletion calculations in Light Water Reactors."
Ann. Nucl. Energy, 139 (2020) 107213.
|
| • |
Garcia, M., Ferraro, D., Valtavirta, V., Tuominen, R., Imke, U., Leppänen, J. and Sanchez-Espinoza, V. (2020b)
"Serpent2-SUBCHANFLOW pin-by-pin modelling capabilities for VVER geometries."
Ann. Nucl. Energy, 135 (2020) 106995.
|
| • |
Gates, J., Denig, A., Ahmed, R., V. Mehta and Kotlyar, D. (2018)
"Low-enriched cermet-based fuel options for a nuclear thermal propulsion engine."
Nucl. Eng. Design, 331 (2018) 313-330.
|
| • |
Gentry, C., George, N., Chvala, O., Maldonado, G. I., Lewis, S., Avigni, P. and Petrovic, B. (2013)
"Core physics parametric studies for liquid salt cooled reactors."
Trans. Am. Nucl. Soc., 108 (2013) 831-833.
|
| • |
Gentry, C., Maldonado, I. and Chvala, O. (2015)
"Burnable Poison Reactivity Control for the Advanced High Temperature Reactor."
Trans. Am. Nucl. Soc., 113 (2015) 1265-1267.
|
| • |
Gentry, C., Maldonado, I. and Kim, K. (2016)
"Development of Two-step Reactor Physics Analysis Procedure for Advanced High Temperature Reactors."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Gentry, C., Godfrey, A., Pandya, T., Davidson, G. and Franceschini, F. (2017a)
"AP1000 Benchmarking of VERA Neutronics Toolset."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Gentry, C., Maldonado, I., Chvala O. and Petrovic, B. (2017b)
"Neutronic Evaluation of a Liquid Salt–Cooled Reactor Assembly."
Nucl. Sci. Eng., 187 (2017) 166-184.
|
| • |
Gentry, C., Kim, K. and Maldonado, I. (2018)
"Two-Step Procedure for Liquid-Salt-Cooled-Reactor Analysis."
Nucl. Sci. Eng., 204 (2018) 299-317.
|
| • |
George, N., Gentry, C., Chvala, O. and Maldonado, G. I. (2013)
"Two dimensional calculations for liquid salt cooled reactors."
Trans. Am. Nucl. Soc., 109 (2013) 1339-1342.
|
| • |
German, P., Aranyosy, A., Böröczki, Z. and Szieberth, M. (2018)
"Sensitivity and Uncertainty Studies for the Alfred Lead Cooled Fast Reactor Core."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Giusti, V. and Montagnini, B. (2019)
"Solution of 3D linearly anisotropic scattering, fixed-source multigroup xyz reactor problems by the AN Boundary Element – Response Matrix method."
Ann. Nucl. Energy, 134 (2019) 205-225.
|
| • |
Gleicher, F., Ortensi, J., Spencer, B., Wang, Y., Novascone, S., Hales, J., Gaston, D., Williamson, R. and Martineau, R. (2014)
"The Coupling of the Neutron Transport Application RattleSNake to the Nuclear Fuels Performance Application Bison Under the Moose Framework."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Gleicher, F., DeHart, M., Ortensi, J., Wang, Y., Alberti, A and Palmer, T. (2015)
"Development of Multi-Physics Methods to Support Restart of the Transient Test Reactor."
Trans. Am. Nucl. Soc., 112 (2015) 711-712.
|
| • |
Glinatsis, G. and Gugiu, D. (2013)
"Coolant void effect investigation case of a Na-cooled fast reactor."
J. Nucl. Research and Devel., 6 (2013) 13-18.
|
| • |
Godfrey, A., Jessee, M., Stimpson, S., Collins, B., Evans, T., Kromar, M., Franceschini, F. and Salazar, D. (2016)
"VERA Benchmarking Results for Krško Nuclear Power Plant Cycle 1."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Gorman, P., Vujic, J. and Greenspan, E. (2015)
"Trade-Off Studies for the Fuel-Self-Sustaining RBWR-Th Core."
Nucl. Technol., 191 (2015) 282-294.
|
| • |
Gorton, J., Collins, B., Nelson, A. and Brown, N. (2019)
"Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR."
Nucl. Eng. Design, 355 (2019) 110317.
|
| • |
Gourbesville, P., Seker, V., Ward, A. and Downar, T. (2017)
"SERPENT-PATHS Coupling Program: Calculations on the RBWR."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Gómez Torres, A., Delfín Loya, A. and del Valle Gallegos, E. (2012)
"Generación de secciones eficaces y soluciones de referencia usando el código Serpent."
In proc. XXIII Congreso Anual de la SNM, Oaxaca, México, Jul. 29 - Aug. 1, 2012 (in Spanish).
|
| • |
Grgic, D., Jecmenica, R. and Pevec, D. (2012)
"Lattice codes pin power prediction comparison."
Nucl. Eng. Design, 246 (2012) 27-40.
|
| • |
Grodzki, M., Darnowski, P. and Niewinski, G. (2018)
"Monte Carlo Analysis of the Battery-Type High Temperature Gas Cooled Reactor."
Archive of Mechanical Engineering, 38 (2017) 209-227.
|
| • |
Groenewald, S., Prinsloo, R., Zamonsky, O. and Tomaševic, D. (2017)
"Practical Semi-Heterogeneous Method in Nodal Core Analysis."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Guglielmelli, A., Rocchi, F. and Sumin, M. (2014)
"SCALE 6.1 Evaluation of the Effective Cross Sections of an LWR Assembly-Reflector Model with Application to the NEA TMI-1 PWR Benchmark."
In proc. 23rd International Conference Nuclear Energy for New Europe 2014, Portoroz, Slovenia, Sept. 8-11, 2014.
|
| • |
Guglielmelli, A., Rocchi, F. and Sumin, M. (2015)
"SCALE 6.1.3 evaluation of the heavy reflector effective cross sections for a GENIII PWR system and a SERPENT 2.1.23 model comparison."
In proc. 24th International Conference Nuclear Energy for New Europe 2015, Portoroz, Slovenia, Sept. 14-17, 2015.
|
| • |
Guglielmelli, A., Rocchi, F. and Bandini, G. (2016)
"SCALE 6.1.3 and Serpent 2.1.24 criticality safety analysis of a Fukushima Daiichi-like Spent Fuel Pool."
In proc. 25th International Conference Nuclear Energy for New Europe 2016, Portoroz, Slovenia, Sept. 5-8, 2016.
|
| • |
Guillard, N., Bernnat, W., Starflinger, J., Zwermann, W. and Pasichnyk, I. (2014)
"Monte Carlo Neutronics Analysis of Sodium-Cooled Fast Reactor Benchmark with Temperature and Burnup Treatment."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Guilliard, N., Bernnat, W., Lapins, J., Pasichnyk, I., Perin, Y., Velkov, K. and Zwermann, W. (2016)
"Analysis of Large Core Neutronics by the Monte Carlo Method Coupled with Thermal Hydraulics."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Gulik, V., Pavlovych, V. and Tkaczyk, A. (2013a)
"Using SERPENT Monte Carlo and Burnup code to model Traveling Wave Reactors (TWR)."
In proc. SNA + MC 2013, Paris, France, Oct. 27-31, 2013.
|
| • |
Gulik, V. and Tkaczyk, A. (2013b)
"Optimization of geometry, material and economic parameters of a two-zone subcritical reactor for transmutation of nuclear waste with SERPENT Monte Carlo code."
In proc. SNA + MC 2013, Paris, France, Oct. 27-31, 2013.
|
| • |
Gulik, V. and Tkaczyk, A. (2014a)
"Cost optimization of ADS design: Comparative study of externally driven heterogeneous and homogeneous two-zone subcritical reactor system."
Nucl. Eng. Design, 270 (2014) 133-142.
|
| • |
Gulik, V., Pavlovych, V. and Tkaczyk, A. (2014b)
"About possibility of analysis of wave passing in Traveling Wave Reactors (TWR) with help of Monte Carlo method."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Gulik, V., Pavlovych, V. and Tkaczyk, A (2014c)
"The Neutron-Physical Model of Two-Zone Research Sub-Critical Reactor for Investigation of Nuclear Waste Transmutation."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Guillard, N., Bernnat, W., Starflinger, J., Zwermann, W. and Pasichnyk, I (2014)
"Monte Carlo Neutronics Analysis of Sodium-Cooled Fast Reactor Benchmark with Temperature and Burnup Treatment."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
György, H. and Czifru, S. (2017)
"Investigation on the potential use of thorium as fuel for the Sodium-cooled Fast Reactor."
Ann. Nucl. Energy, 103 (2017) 238-250.
|
| • |
Hall, A., Xu, Y., Ward, A., Downar, T., Shirvan, K. and Kazimi, M. (2013)
"Advanced neutronics methods for analysis of the RBWR-AC."
Trans. Am. Nucl. Soc., 108 (2013) 771-774.
|
| • |
Hall, A., Downar T., Ward A., Jarret M., Wysocki A., Xu Y. and Shirvan K. (2014)
"Advanced Methods Development for Equilibrium Cycle Calculations of the RBWR."
In proc. ICAPP 2014, Charlotte, NC, Apr. 6-9, 2014.
|
| • |
Hannstein, V., Behler, M. and Sommer, F. (2017)
"MOTIVE - A New Modular Burn-up Code."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Haroon, J. Kicka, L., Mohapatra, S., Nichita E. and Schwanke, P. (2016)
"Comparison of the Reactivity Effects Calculated by DRAGON and Serpent for a PHWR 37-Element Fuel Bundle."
ASME J. of Nuclear Rad. Sci., 3 (2016) 011011.
|
| • |
Harrisson, G. and Marleau, G. (2012)
"Computation of a Canadian SCWR unit cell with deterministic and Monte Carlo codes."
In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
|
| • |
Harrisson, G. and Marleau, G. (2013)
"Simulation strategy for the evaluation of neutronic properties of a Canadian SCWR fuel channel."
Sci. Technol. Nucl. Install., 2013 (2013), Article ID 352757.
|
| • |
Hartanto, D., Kim, Y. and Venneri, F. (2015)
"Neutronics evaluation of a super-deep-burn with TRU Fully Ceramic Microencapsulated (FCM) fuel in CANDU."
Prog. Nucl. Energy, 83 (2015) 261-269.
|
| • |
He, D. and Walters, W. (2018a)
"A New Fission Matrix Correction Method to Estimate the Source Distribution in Nuclear Reactor Core."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
He, D. and Walters, W. (2018b)
"Application of the Ratio Correction Fission Method to a 2-D Four-Assembly Model."
Trans. Am. Nucl. Soc., 118 (2018) 917-920.
|
| • |
He, D. and Walters, W. (2019)
"A local fission matrix correction method for heterogeneous whole core transport with RAPID."
Ann. Nucl. Energy, 134 (2019) 263-272.
|
| • |
Hébert, A. (2016)
"DRAGON5 and DONJON5, the contribution of École Polytechnique de Montréal to the SALOME platform."
Ann. Nucl. Energy, 87 (2016) 12-20.
|
| • |
Helgesson, P., Rochman, D., Sjöstrand, H., Alhassan E. and Koning, A. (2014)
"UO2 Versus MOX: Propagated Nuclear Data Uncertainty for keff, with Burnup."
Nucl. Sci. Eng., 177 (2014) 321-336.
|
| • |
Helgesson, P., Sjöstrand, H., Koning, A., Rydén, J., Rochman, D., Alhassan, E. and Pomp, S. (2017)
"Combining Total Monte Carlo and Unified Monte Carlo: Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances."
Prog. Nucl. Energy, 96 (2017) 76-96.
|
| • |
Hellesen, C., Wolniewicz, P., Jansson, P., Håkansson, A., Svärd, S. and Österlund, M. (2014)
"Transient Simulation of Gas Bubble in a Medium Sized Lead Cooled Fast Reactor."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
|
| • |
Hellesen, C., Grape, S., Jansson, P., Jacobsson Svärd, Åberg Lindell, and Andersson, P. (2017)
"Nuclear spent fuel parameter determination using multivariate analysis of fission product gamma spectra."
Ann. Nucl. Energy, 110 (2017) 886-895.
|
| • |
Henrice, E., Palma, D., Gonçalves, A. and Mesquita, A. (2015)
"Neutronic Flux Analysis In Subcritical Systems Using The R/S And DFA Methods."
Trans. Am. Nucl. Soc., 113 (2015) 1317-1320.
|
| • |
Henrice, E., Palma, D., Goncalves, A. and Mesquita, A. (2017)
"Support to the identification of anomalies in an external neutron source using Hurst Exponents."
Prog. Nucl. Energy, 99 (2017) 119-126.
|
| • |
Henry, R. and Seubert, A. (2019)
"3-D Modelling of a Superphénix Benchmark with SERPENT and PARCS for coupled simulation with PARCS/ATHLET."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
|
| • |
Heo, W. and Kim, Y. (2016)
"Position-Dependency of Fuel Assembly Homogenization in a Pressurized Water Reactor."
Trans. Am. Nucl. Soc., 113 (2016) 761-764.
|
| • |
Heo, W. and Kim, Y. (2018)
"A Diffusion-based 3D FEM Analysis for Assessment of Reactivity Change due to Support Plate Expansion and Localized Flowering in an SFR."
Trans. Am. Nucl. Soc., 119 (2018) 1245-1248.
|
| • |
Herman, B., Shwageraus, E., Leppänen, J. and Forget, B. (2011)
"Cross section generation strategy for advanced LWRs."
In proc. ICAPP 2011, Nice, France, May 2-5, 2011.
|
| • |
Hernández, A., Torres, A. del Valle Gallegos, E. (2017)
"HPC implementation in the time-dependent neutron diffusion code AZKIND."
Ann. Nucl. Energy, 99 (2017) 174-182.
|
| • |
Hernandez, R., Brown, N. and Todosow, M. (2018)
"Fuel Cycle Performance of Russian Floating Small Modular Reactor Concepts with Enrichments from 5-20%."
Trans. Am. Nucl. Soc., 119 (2018) 209-211.
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| • |
Hernandez, E., Todosow, M. and Brown, N. (2019)
"Micro heat pipe nuclear reactor concepts: Analysis of fuel cycle performance and environmental impacts."
Ann. Nucl. Energy, 126 (2019) 419-426.
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| • |
Herrero, J., Vasiliev, A., Pecchia, M., Ferroukhi, H. and Caruso, S. (2016)
"Review calculations for the OECD/NEA Burn-up Credit Criticality Safety Benchmark"
Ann. Nucl. Energy, 87 (2016) 48-57.
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| • |
Hidayatullah, R. and Kim, Y. (2013a)
"Feasibility of Coated Particle Fuel for a High-Performance, Ultra-Safe Research Reactor."
In proc. Transactions of RRFM2013, Saint Petersburg, Russia, Apr. 21-25, 2013.
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| • |
Hidayatullah, R. and Kim, Y. (2013b)
"A Novel Plate Fuel Concept Based on Coated Particle for Research Reactor."
Trans. Korean Nucl. Soc., Spring Meeting, Gwangju, Korea, May 30-31, 2013.
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| • |
Hidayatullah, R. and Kim, Y. (2013c)
"A new coated UO2 particle fuel for ultra-high performance research reactor."
Trans. Am. Nucl. Soc., 108 (2013) 759-760.
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| • |
Hidayatullah, R. and Kim, Y. (2013d)
"Preliminary Study of Plate Fuel Concept Based on Coated Particle Fuel for Research Reactor."
In proc. IGORR 2013 and IAEA Technical Meeting, Daejeon, Korea, Oct.r 13-18, 2013.
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| • |
Hidayatullah, R., Hartanto, D. and Kim, Y. (2015)
"A novel research reactor concept based on coated particle fuel"
Ann. Nucl. Energy, 77 (2015) 477-486.
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| • |
Hill, I., Soppera, N. and Bossant, M. (2014)
"IDAT: The International Handbook of Evaluated Reactor Physics Benchmark Experiments Database and Analysis Tool."
Nucl. Sci. Eng, 178 (2014) 280-294.
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| • |
Hino, T., Miwa, J., Mitsuyasu, T., Ishii, Y., Ohtsuka, M., Moriya, K., Shirvan, K., Seker, V., Hall, A., Downar, T., Gorman, P., Fratoni M. and Greenspan, E. (2017)
"Core Design and Analysis of Axially Heterogeneous Boiling Water Reactor for Burning Transuranium Elements."
Nucl. Sci. Eng., 187 (2017) 213-239.
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| • |
Hiscox, B. and Shirvan, K. (2016)
"Neutronics Analysis of Fuel-in-fiber Concept."
Trans. Am. Nucl. Soc., 115 (2016) 1351-1354.
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| • |
Hiscox, B. and Shirvan, K. (2019)
"Reactor physics analysis of a new Accident Tolerant Fuel called Fuel-in-Fibers."
Ann. Nucl. Energy, 130 (2019) 473-482.
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| • |
Holt, L., Schubert, A., Van Uffelen, P., Walker, C., Fridman, E. and Sonoda, T. (2014)
"Sensitivity study on Xe depletion in the high burn-up structure of UO2."
J. Nucl. Mat., 452 (2014) 166-172.
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| • |
Hombourger, B., Krepel, J., Mikityuk, K. and Pautz, A. (2015)
"Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor."
ASME J. of Nuclear Rad Sci., 1 (2015) 011009.
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| • |
Hombourger, B., Krepel, J., Mikityuk, K. and Pautz, A. (2017)
"On the Feasibility of Breed-and-Burn Fuel Cycles in Molten Salt Reactors."
In proc. FR17, Yekaterinburg, Russia, Jun. 26-29, 2017.
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| • |
Hou, J., Heidet, F., Gorman, P. and Greenspan, E. (2014)
"On Multi-Group Cross Sections for Breed-and-Burn Reactors."
Trans. Am. Nucl. Soc., 111 (2014) 1267-1270.
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| • |
Hou, J., Choi, H. and Ivanov, K. (2015)
"Development of an iterative diffusion-transport method based on MICROX-2 cross section libraries."
Ann. Nucl. Energy, 77 (2015) 335-342.
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| • |
Huang, D. and Abdel-Khalik, H. (2019)
"Investigative Study on Impact of Modeling Uncertainties in Uncertainty Quantification of Neutronics Core Simulation."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Hursin, M., Vasiliev, A., Ferroukhi, H. and Pautz, A. (2013)
"Comparison of Serpent and CASMO-5M for pressurized water reactors models."
In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
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| • |
Hursin, M., Rossinelli, L., Ferroukhi, H. and Pautz, A. (2015)
"BWR Full Core Analysis with Serpent/Simulate-3 Hybrid Stochastic/Deterministic Code Sequence."
In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
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| • |
Hussein, M., Lewis, N. and Bonin, H. (2013)
"Numerical verification/validation of the theory of coupled reactors for deuterium critical assembly, using MCNP5 and Serpent codes."
In proc. 12th International Conference on CANDU Fuel, Kingston, ON, Canada, Sept. 15-18, 2013.
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| • |
Hussein, M., Bonin, H., Lewis B. and Chan P. (2015)
"Design of a Multi-Spectrum CANDU-Based Reactor, MSCR, With 37-Element Fuel Bundles Using SERPENT Code."
In proc. 7ICMSNSE, Ottawa, ON, Oct. 18-21, 2015.
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| • |
Ilas, G, Gauld, I., Sunny, E., Westfall, M. and Nguyen, J. (2015)
"Modeling and Simulation of Hanford B Reactor Experiments."
In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
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| • |
Ipbüker, C., Nulk, H., Gulik, V., Biland, A. and Tkaczyk, A. (2015)
"Radiation shielding properties of a novel cement–basalt mixture for nuclear energy applications."
Nucl. Eng. Design, 284 (2015) 27-37.
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| • |
Ivanov, V. and Bousquet J. (2016)
"Assessing reactor physics codes capabilities to simulate fast reactors on the example of the BN-600 Benchmark."
Kerntechnik, 81 (2016) 512-519.
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| • |
Jamalipour, M., Cammi, A. and Ricotti, M. (2018)
"The application of nodal method for dynamic analysis of TRIGA Mark II."
Ann. Nucl. Energy, 116 (2018) 360-375.
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| • |
Jamil, Z., Wu, B., Yu, S., Yang, Q., Khan, M., Ali, M. and Hu, L. (2018)
"Detailed neutronic analysis of a MOX-fueled metal-cooled reactor."
Ann. Nucl. Energy, 114 (2018) 427-436.
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| • |
Jang, J., Kim, W., Jeong, S., Jeong, E., Park, J., Lemaire, M., Lee, H., Jo, Y., Zhang, P. and Lee, D. (2018)
"Validation of UNIST Monte Carlo code MCS for criticality safety analysis of PWR spent fuel pool and storage cask."
Ann. Nucl. Energy, 114 (2018) 495-509.
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| • |
Jareteg, K., Vinai, P. and Demaziére, C. (2013)
"Investigation of the possibility to use a fine-mesh solver for resolving coupled neutronics and thermal-hydraulics."
In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
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| • |
Jareteg, K., Vinai, P. and Demaziére, C. (2014a)
"Fine-mesh deterministic modeling of PWR fuel assemblies: Proof-of-principle of coupled neutronic/thermal–hydraulic calculations."
Ann. Nucl. Energy, 68 (2014) 247–256.
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| • |
Jareteg, K., Vinai P., Demazière, C. and Sasic, S. (2014b)
"Influence of an SN Solver in a Fine-Mesh Neutronics/Thermal-Hydraulics Framework."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Jo, Y., Hursin, M., Lee, D., Ferroukhi, H. and Pautz, A. (2018)
"Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code."
Ann. Nucl. Energy, 111 (2018) 141-151.
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| • |
Johns, J. and Tsvetkov, P. (2012)
"Autonomous corium reactor for terrestrial applications."
In proc. ICONE20, Anaheim, CA, Jul. 30 - Aug. 3, 2012.
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Johns, J., Valtavirta, V. and Lenard, R. (2015)
"Dynamic Simulation of Nuclear Reactors Experiencing High Rates of Deformation."
Trans. Am. Nucl. Soc., 112 (2015) 711-712.
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| • |
Johnson, A. and Kotlyar, D. (2018)
"Comparative Study of Monte Carlo Burnup Schemes for Full Core Calculations."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Johnson, A. and Kotlyar, D. (2019a)
"SERPENT-Tools: A Python Package for Expediting Analysis with SERPENT Data."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Johnson, A. and Kotlyar, D. (2019b)
"Prediction of Spatial Flux Through Depletion."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Jolodosky, A., Aufiero, M. and Fratoni, M. (2019)
"Exact perturbation theory for fusion blanket design."
Ann. Nucl. Energy, 131 (2019) 353-366.
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Juárez-Martínez, L. and Francois, J. (2017)
"Study on the use of Thorium in a Lead-Cooled Fast Reactor."
Trans. Am. Nucl. Soc., 117 (2017) 1273-1277.
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Juárez-Martínez, L. and Francois, J. (2018)
"Comparative neutronic study of homogeneous and heterogeneous thorium fuel based core design in a lead-cooled fast reactor."
Ann. Nucl. Energy, 114 (2018) 102-109.
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Juutilainen, P. (2008)
"Simulating the behaviour of the fast reactor JOYO."
In proc. IYNC-2008, Interlaken, Switzerland, Sept. 20-26, 2008.
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Juutilainen, P. and Viitanen, T. (2013)
"An Assessment of the Effect on Olkiluoto Repository Capacity Achievable with Advanced Fuel Cycles."
In proc. Global 2013, Salt Lake City, UT, Sept. 29 - Oct. 3, 2013.
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| • |
Kaffezakis, N. and Kotlyar, D. (2017)
"Fuel Cycle Analysis for Modified High Conversion LWR Assembly."
Trans. Am. Nucl. Soc., 117 (2017) 257-260.
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| • |
Kasselmann, S., Schitthelm, O., Tantillo, F., Scholthaus, S., Rössel, C. and Allelein, H. (2016)
"Development of a new nuclide generation and depletion code using a topological solver based on graph theory."
Nucl. Eng. Design, 306 (2016) 154-159.
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| • |
Kasselmann, S., Xhonneux, A., Tantillo, F., Trabadela, A., Lambertz, D. and Allelein, H. (2016)
"V&V of the HTR Code Package (HCP) as a comprehensive HTR steady state and transient safety analysis framework."
In proc. HTR 2016, Las Vegas, NV, Nov. 6-10, 2016.
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| • |
Kasselmann, S., Xhonneux, A., Tantillo, F., Trabadela, A., Lambertz, D. and Allelein, H. (2018)
"Verification of the HTR code package (HCP) as a comprehensive HTR steady state and transient safety analysis framework."
Nucl. Eng. Design, 329 (2018) 167-176.
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| • |
Keckler, C., Fratoni, M. and Greenspan, E. (2018)
"On the Importance of Control Assembly Layouts in Standing Wave B&B Cores."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Keckler, C., Fratoni, M. and Greenspan, E. (2019)
"Uncertainty in the DPA of a B&B Core Due to Uncertainty in the Neutron Spectrum."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Kelsey, J., Morell-Pacheco, A., Hughes, T., Whitman, N. and Tsvetkov, P. (2016)
"VASIMR Interfaced High Temperature Gas-Cooled Fast Reactor for Space Applications."
Trans. Am. Nucl. Soc., 115 (2016) 80-83.
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Kepisty, G. and Cetnar, J. (2017)
"On the discrepancies between FIMA and specific burnup."
Prog. Nucl. Energy, 98 (2017) 187-192.
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Kerby, L., Tumulak, A., Leppänen, J. and Valtavirta, V. (2017)
"Preliminary Serpent–MOOSE Coupling and Implementation of Functional Expansion Tallies in Serpent."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Kim, J. and Kim, Y. (2015)
"Xe-135m Impact on the PCR Measurement of CANDU6 Core."
Trans. Am. Nucl. Soc., 112 (2015) 682-684.
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Kim, J., Kim Y. and Kim, K. (2015)
"Modelling of Xe-135m for Evaluation of the CANDU6 Power Coefficient of Reactivity."
In proc. 7ICMSNSE, Ottawa, ON, Oct. 18-21, 2015.
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| • |
Kim, J., Motalab, M., Y. Kim and G. Kim (2018)
"Measurement and Analysis for Determination of PCR of the CANDU6 Core."
Nucl. Technol., 201 (2018) 138-154.
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| • |
Kim, K., Hu, J. and Gentry, C. (2016)
"Embedded Self-Shielding Method Applied to Doubly Heterogeneous Fully Ceramic Micro-Encapsulated Fuels."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Kim, K., Lee, D., Shim, H. and Pawel, A. (2018)
"VERA DeplETION Benchmarks by CASL VERA, Serpent abd MCCARD with ENDF/B-VII.0 and VII.1."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Kim, K., Williams, M., Holcomb, A., Wiarda, D., Jeon, B. and Yang, W. (2018)
"The AMPX/SCALE Multigroup Cross Section Processing for Fast Reactor Analysis."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Kim, K., Gentry, C., Godfrey, A., Liu, Y. and Palmtag, S. (2019)
"Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification."
Ann. Nucl. Energy, 132 (2019) 1-23.
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Kim, K., Williams, M., Holcomb, A., Wiarda, D., Jeon, B. and Yang, W. (2019)
"The SCALE/AMPX multigroup cross section processing for fast reactor analysis."
Ann. Nucl. Energy, 132 (2019) 161-171.
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| • |
Kim, S., Oh, B., Cho, S., Baik, S., You, H., Moon, J. and Lee, J. (2016)
"Conceptual System Design of a Supercritical CO2 cooled Micro Modular Reactor."
In proc. HTR 2016, Las Vegas, NV, Nov. 6-10, 2016.
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Kim, W., Hartanto, D. and Kim, Y. (2012)
"Comparative Evaluation of Fuel Temperature Coefficient of Standard and CANFLEX Fuels in CANDU 6."
Trans. Korean Nucl. Soc., Autumn Meeting, Gyeongju, Korea, Oct. 25-26, 2012.
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Kim, W. and Kim, Y. (2013b)
"Improvement of Safety Parameters by Using Erbium-loaded CANFLEX Fuel Bundle in the CANDU Reactor."
In proc. ICAPP 2013, Jeju, Korea, Apr. 14-18, 2013.
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Kim, W. and Kim, Y. (2013c)
"Application of the 3-D Nodal Equivalence Theory to the CANDU Reactor."
Trans. Korean Nucl. Soc., Spring Meeting, Gwangju, Korea, May 30-31, 2013.
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Kim, W. and Kim, Y. (2013d)
"A Novel Utilization of Er Burnable Absorber for Improvement of CANDU Safety Parameters."
Trans. Am. Nucl. Soc., 108 (2013) 714-715.
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Kim, W., Park, J. Kozlowski, T. Lee, Y. and Lee, D. (2015)
"Comparative Neutronics Analysis of DIMPLE S06 Criticality Benchmark with Contemporary Reactor Core Analysis Computer Code Systems"
Sci. Technol. Nucl. Install., 2015 (2015), Article ID 180979.
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Kim, W., Motalab, M., Bae, J. and Kim, Y. (2016)
"mprovement of CANDU safety parameters by using the CANFLEX fuel."
Ann. Nucl. Energy, 94 (2016) 793-801.
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| • |
Kim, W., Reitsma, F. and Lee, D. (2016)
"IAEA Coordinated Research Program on HTGR Uncertainty Analysis: Results of Exercise I-1 Model and the Application of the RPT Method."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Kloosterman, J., Huisman M. and Rohde M. (2014)
"Preliminary Design of the Delft Isotope Production Reactor (DIPR)."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Knebel, M., Mercatali, L., Sanchez, V., Stieglitz, R. and Macian-Juan, R. (2016)
"Validation of the Serpent 2-DYNSUB code sequence using the Special Power Excursion Reactor Test III (SPERT III)."
Ann. Nucl. Energy, 91 (2016) 79-91.
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Kochetkov, A., Krása, A., Vittiglio, G., Wagemans, J., Bianchini, A., Fabrizio, V., Carta, M. Firpo, G., Fridman, E., Sarotto, M. and Bécares, V. (2016)
"Spectrun Index and Minor Actinide Fission Rate Measurements in Several Fast Lead Critical Cores in the Zero Power VENUS-F Reactor."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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Kodeli, I., Aufiero, M. and Zwermann, W. (2016a)
"Comparison of Deterministic and Monte Carlo codes SUSD3D, Serpent AND XSUSA for Beta-effective Sensitivity Calculations."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Kodeli, I., Mastrangelo, V., Ivanov, E., Aures, A., Zwermann, W., Aufiero, M., Peneliau, Y., Ivanov, K. and Sartori, E. (2016b)
"OECD/NEA Intercomparison of Deterministic and Monte Carlo Cross-section Sensitivity Codes Using SNEAK-7 Benchmarks."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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Kodeli, I. and Slavic, S. (2017)
"SUSD3D Computer Code as Part of the XSUN-2017 Windows Interface Environment for Deterministic Radiation Transport and Cross-Section Sensitivity-Uncertainty Analysis."
Sci. Technol. Nucl. Install., 2017 (2017), Article ID 1264736.
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| • |
Korkmaz, M., Yigit, M. and Agar, O. (2013)
"Burnup calculations using Serpent code in accelerator driven thorium reactors."
Kerntechnik, 78 (2013) 193-197.
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| • |
Korkmaz, M., Agar, O. and Buyuker, E. (2014)
"Burnup analysis of the VVER-1000 reactor using thorium-based fuel."
Kerntechnik, 79 (2014) 478-483.
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| • |
Korkut, T., Kara, A. and Korkut, H. (2016)
"Effect of ultra high temperature ceramics as fuel cladding materials on the nuclear reactor performance by SERPENT Monte Carlo code."
Kerntechnik, 81 (2016) 599-608.
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| • |
Kotlyar, D. and Shwageraus, E. (2012)
"Comparison of square and hexagonal fuel lattices for high conversion PWRs."
Kerntechnik, 77 (2012) 292-299.
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Kotlyar, D. and Shwageraus, E. (2013)
"On the use of predictor-corrector method for coupled Monte Carlo burnup codes."
Ann. Nucl. Energy, 58 (2013) 228-237.
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Kotlyar, D., Aufiero, M., Shwageraus, E. and Fratoni, M. (2017a)
"A perturbation-based susbtep method for coupled depletion Monte-Carlo codes."
Ann. Nucl. Energy, 102 (2017) 236-244.
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Kotlyar, D., Lindley, B. and Mohamed, H. (2017b)
"Improving fuel utilization in SmAHTR with spectral shift control design: Proof of concept."
Ann. Nucl. Energy, 104 (2017) 53-63.
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| • |
Kotlyar, D., Aufiero, M., Shwageraus, E. and Fratoni, M. (2017)
"Iteration-Free Coupled Monte Carlo with Thermal Hydraulic Method."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Kotlyar, D., Aufiero, M., Shwageraus, E. and Fratoni, M. (2017)
"Stable perturbation-based susbtep method for coupled Monte Carlo Codes."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Kowalski, M. and Shwageraus, E. (2018)
"Accelerating Monte Carlo By variable Fidelity: First Results."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Krepel, J., Hombourger, N., Fiorina, C., Mikityuk, K., Rohde, U., Kliem, S. and Pautz, A. (2014)
"Fuel cycle advantages and dynamics features of liquid fueled MSR."
Ann. Nucl. Energy, 64 (2014) 380-397.
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Krepel, J., Mikityuk, K., Hombourger, B., Pautz, A., Zanetti, M., Aufiero, M. and Luzzi, L. (2014)
"Hybrid Spectrum Molten Salt Reactor."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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Krepel, J. and Losa, E. (2019)
"Closed U-Pu and Th-U cycle in sixteen selected reactors: Comparison of major equilibrium features."
Ann. Nucl. Energy, 128 (2019) 341-357.
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Kumar, A. and Tsvetkov, P. (2015a)
"A new approach to nuclear reactor design optimization using genetic algorithms and regression analysis."
Ann. Nucl. Energy, 85 (2015) 27-35.
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Kumar, A. and Tsvetkov, P. (2015b)
"Parametric Analysis and Optimization using Multivariate Regression Analysis and Genetic Algorithms."
Trans. Am. Nucl. Soc., 112 (2015) 148-152.
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Kumar, A. and Tsvetkov, P. (2015c)
"Optimization of U–Th fuel in heavy water moderated thermal breeder reactors using multivariate regression analysis and genetic algorithms."
Ann. Nucl. Energy, 85 (2015) 885-892.
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Kumar, A. and Tsvetkov, P. (2016)
"An Iterative Optimization Strategy for Nuclear Reactor Design."
Trans. Am. Nucl. Soc., 113 (2016) 242-245.
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Kunchev, T., Shwageraus E. and Leppänen, J. (2019)
"Energy-Dependent Fission Yields in Advanced Reactors."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Kuopanportti, J., Saarinen, S., Lahtinen, T. and Ekström, K. (2017)
"New engineering safety factors for Loviisa NPP core calculations."
Kerntechnik, 82 (2017) 390-395.
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| • |
Kuopanportti, J., Saarinen, S. and Leppänen, J. (2018)
"Assessment of Serpent Cross Sections of the Second Generation Fuel of TVEL for Loviisa NPP."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Labarile, A., Olmo, N., Miró, R., Barrachina, T. and Verdú, G. (2016)
"Comparison of SERPENT and SCALE methodology for LWRs transport calculations and additionally uncertainty analysis for cross-section perturbation with SAMPLER module."
EPJ Nuclear Sci. Technol., 2 (2016) Article 11.
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| • |
Laboure, V., Ortensi, J., Wang, Y., Schunert, S. and DeHart, M. (2018)
"Iterated Discontinuity Factors Based or Reference Outgoing Currents for Discontinuous Finite Element Diffusion."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Labouré, V., Wang, Y., Ortensi, J., Schunert, S., Gleicher, F., DeHart, M. and Martineau, R. (2019)
"Hybrid super homogenization and discontinuity factor method for continuous finite element diffusion."
Ann. Nucl. Energy, 128 (2019) 443-454.
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| • |
Laboure, V., Ortensi, J., Wang, Y., Schunert, S., Gleicher, F., DeHart, M. and Martineau, R. (2019)
"Multiphysics Steady-State Simulation the High Temperature Test Reactor with MAMMOTH, BISON and RELAP-7."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Lahtinen, T. (2014)
"Solution of the CB6 benchmark on VVER-440 final disposal using the Serpent reactor physics code."
Kerntechnik, 79 (2014) 303-313.
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| • |
Lajoie M., Marleau G., Martin. N. and Hébert A. (2010)
"Application of 3D Collision Probability Method to VHTR Spherical Geometries."
In proc. PHYSOR 2010, Pittsburgh, PA, May 9-14, 2010.
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| • |
Laureau, A., Aufiero, M., Rubiolo, P., Merle-Lucotte, E. and Heuer, D. (2015a)
"Coupled Neutronics and Thermal-hydraulics Transient Calculations Based on a Fission Matrix Approach: Application to the Molten Salt Fast Reactor."
In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
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| • |
Laureau, A., Aufiero, M., Rubiolo, P., Merle-Lucotte, E. and Heuer, D. (2015b)
"Transient Fission Matrix: Kinetic calculation and kinetic parameters Β_eff and Λ_eff calculation."
Ann. Nucl. Energy, 85 (2015) 1035-1044.
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Laureau, A., Heuer, D., Merle-Lucotte, E., Rubiolo, P., Allibert, M. and Aufiero, M. (2017a)
"Transient coupled calculations of the Molten Salt Fast Reactor using the Transient Fission Matrix approach."
Nucl. Eng. Design, 316 (2017) 112-124.
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| • |
Laureau, A., Buiron, L., Fontaine, B. and Pascal, V. (2017b)
"Fission Matrix Interpolation for the TFM Approach Based on a Local Correlated Sampling Technique for Fast Spectrum Heterogeneous Reactors."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Laureau, A., Lederer, T., Krakovich, A., Buiron, L. and Fontaine, B. (2017c)
"Transient coupled neutronics-thermalhydraulics study of ULOF accidents in sodium fast reactors using spatial kinetics: comparison of the TFM Monte Carlo and SN approaches."
In proc. ICAPP 2017, Fukui and Kyoto, Japan, Apr. 24-28, 2012.
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| • |
Laureau, A., Buiron, L. and Fontaine, B. (2017d)
"Local correlated sampling Monte Carlo calculations in the TFM neutronics approach for spatial and point kinetics applications."
EPJ Nuclear Sci. Technol., 3 (2017) Article 16.
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| • |
Laureau, A., Buiron, L. and Fontaine, B. (2017e)
"Towards spatial kinetics in a low void effect sodium fast reactor: core analysis and validation of the TFM neutronic approach."
EPJ Nuclear Sci. Technol., 3 (2017) Article 17.
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| • |
Laureau, A., Lederer, Y., Krakovich, A., Buiron, L. and Fontaine, B. (2018)
"Spatial analysis of unprotected transients in heterogeneous sodium fast reactors."
Ann. Nucl. Energy, 115 (2018) 554-564.
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| • |
Laureau, A., Lamirand, V., Rochman, D. and Pautz, A. (2019a)
"Bayesian Monte Carlo assimilation for the PETALE experimental programme using inter-dosimeter correlation."
In proc. Nuclear Data (ND2019), Beijing, China, May 19-24, 2019.
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| • |
Laureau, A., Lamirand, V., Rochman, D. and Pautz, A. (2019b)
"Total Monte Carlo acceleration for the PETALE experimental programme in the CROCUS reactor."
EPJ Web of Conferences 2011, 03002 (2019).
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| • |
Laureau, A., Lamirand, V., Rochman, D., Perret, G., Gruel, A., Leconte, P., Blaise, P. and Pautz, A. (2019c)
"An Experimental Programme optimized with Uncertainty Propagation: PETALE in the CROCUS Reactor."
EPJ Web of Conferences 2011, 03003 (2019).
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| • |
Laureau, A., Lamirand, V., Rochman, D. and Pautz, A. (2020a)
"Uncertainty propagation based on correlated sampling technique for nuclear data applications."
EPJ Nuclear Sci. Technol., 6 (2020) Article 8.
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| • |
Laureau, A., Lamirand, V., Rochman, D. and Pautz, A. (2020b)
"Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor."
EPJ Nuclear Sci. Technol., 6 (2020) Article 9.
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| • |
Lee, Y. and Cho, N. (2014)
"Comparison of Two-Temperature Homogenized Model, Harmonic- and Volumetric-Average Thermal Conductivity Models on Transient Analysis of Fully Ceramic Microencapsulated Fuel."
Trans. Am. Nucl. Soc., 111 (2014) 1562-1562.
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Lee, Y. and Cho, N. (2015)
"Steady- and transient-state analyses of fully ceramic microencapsulated fuel loaded reactor core via two-temperature homogenized thermal-conductivity model."
Ann. Nucl. Energy, 76 (2015) 283-296.
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| • |
Lee, C., Jung, Y., Connaway H. and Taiwo, T. (2017)
"Simulation of TREAT Cores Using High-fidelity Neutronics Code PROTEUS."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Leray, O., Pecchia, M., Vasiliev, A., Ferroukhi, H., Pautz A. and Perrier, H. (2015)
"Development, Verivication and Test Application of a Hybrid CASMO-5/Serpent Depletion Scheme."
In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
|
| • |
Leray, O., Fiorito, L., Rochman, D., Ferroukhi, H., Pautz, A., Stankovskiy, A. and Van den Eynde, G. (2016)
"Comparison of Fission Yield Perturbation Methodologies on Nuclide Composition for a PWR UO2 Fuel Assembly."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Leray, O., Fiorito, L., Rochman, D., Ferroukhi, H., Stankovsky, A. and Van den Eynde, G. (2017)
"Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly."
Prog. Nucl. Energy, 101 (2017) 486-495.
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| • |
Levinsky, A., Adams, F., Golesorkhi, S., Trottier, A., Roubtsov, D. and Alexander, J. (2018a)
"Comparison of the Main Operational Characteristics of the Lead-Cooled, Gas-Cooled and Molten Salt Small Modular Reactor Concepts."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Levinsky, A., Roubtsov, D., Adams, F. and Trottier, A. (2018b)
"Effect of Uncertainties in U(n,g) Cross Section on a Lead-Cooled Reactor Transient."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Levinsky, A., Valtavirta, V., Adams, F., and Anghel, V. (2019)
"Modeling of the SPERT transients using Serpent 2 with time-dependent capabilities."
Ann. Nucl. Energy, 125 (2019) 80-98.
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| • |
Li, J., Rochman, D., Herrero, J., Vasiliev, A., Ferroukhi, H., Pautza, A., Seidl, M. and Janin, D. (2017a)
"UO2 fuel pin bowing effects on isotopic concentrations."
Ann. Nucl. Energy, 105 (2017) 361-368.
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| • |
Li, J., Rochman, D., Vasiliev, A., Ferroukhi, H., Herrero, J., Pautza, A., Seidl, M;. and Janin, D. (2017b)
"Bowing effects on isotopic concentrations for simplified PWR assemblies and full cores."
Ann. Nucl. Energy, 110 (2017) 1023-1029.
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| • |
Li, J.-Y. Gu, L., Xu H.-S., Korepanova, N., Yu R., Zhu, Y.-L. and Qin, C.-P. (2018)
"CAD modeling study on FLUKA and OpenMC for accelerator driven system simulation."
Ann. Nucl. Energy, 114 (2018) 329-341.
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| • |
Li, Y., Wang, D., Wu, H. and Shen, W. (2018)
"Analysis of Two-Dimensional Full-Core One-Step Calculation with Bamboo-Lattice."
Trans. Am. Nucl. Soc., 118 (2018) 900-902.
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| • |
Li, Z., Cao, L., Wu, H., He, Q. and Shen, W. (2016)
"On the improvements in neutronics analysis of the unit cell for the pebble-bed fluoride-salt-cooled high-temperature reactor."
Prog. Nucl. Energy, 93 (2016) 287-296.
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| • |
Li, Z., Cai, J., Zeng, Q., Li, Z., Wang, Y. (2019)
"The preliminary neutronics analysis for a 10 MW molten salt reactor with solid fuel."
Prog. Nucl. Energy, 110 (2019) 325-332.
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| • |
Liem, P., Hartanto, D. and Kim, Y. (2016)
"Impact of new evaluated nuclear data libraries on core characteristics of innovative reactor designs."
Prog. Nucl. Energy, 87 (2016) 74-88.
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| • |
Lima-Reinaldo, Y., Francois, J., Martín-del-Campo, C. (2019)
"Analysis of the use of thorium in the GFR2400 gas-cooled fast reactor."
Nucl. Eng. Design, 343 (2019) 11-21
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| • |
Lindley, B., Ahmad, A., Zainuddin, N. Franchescini, F. and Parks, G. (2014a)
"Steady-state and transient core feasibility analysis for a thorium-fuelled reduced-moderation PWR performing full transuranic recycle."
Ann. Nucl. Energy, 72 (2014) 320-337.
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| • |
Lindley, B., Fiorina, C., Franchescini, F., Lahoda, E. and Parks, G. (2014b)
"Thorium breeder and burner fuel cycles in reduced-moderation LWRs compared to fast reactors."
Prog. Nucl. Energy, 77 (2014) 107-123.
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| • |
Lindley, B. and Parks, G. (2014c)
"Axially Heterogeneous Thorium Fuel Designs for Transuranic Burning in Reduced-Moderation BWRs."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Lindley, B., Kotlyar, D., Parks, G., Lillington, J. and Petrovic, B. (2016)
"Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes."
EPJ Nuclear Sci. Technol., 2 (2016) Article 14.
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| • |
Liponi, L., Taforeau, J. and Hébert, A. (2017)
"Calculation and Verification of Assembly Discontinuity Factors for the DRAGON/PARCS code sequence."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Liponi, L. and Taforeau, J. (2018)
"Analysis of the MIT BEAVRS Benchmark Cycle 1 Using the DRAGON5/PARCS Code Sequence."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Lomonaco, G., Borreani, W., Caiffi, B. and Chersola, D.
"A short overview of ITER-like pulsed MCF reactors application as hybrid nuclear systems for actinides transmutation."
In proc. FUNFI2, Rome, Italy, Oct. 26-28, 2014.
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| • |
Lopez-Solis, R., François, J., Bastida-Ortiz, G., Becker, M. and Sánchez-Espinoza, V. (2016)
"Fuel depletion analysis of a small sodium fast reactor with KANEXT and SERPENT."
Ann. Nucl. Energy, 98 (2016) 26-35.
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López, M., Buck, M. and Starflinger, J. (2018)
"Neutronic Modelling of Fuel Debris for a Criticality Evaluation."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Lorenzi, S. (2018)
"An Adjoint Proper Orthogonal Decomposition method for a neutronics reduced order model."
Ann. Nucl. Energy, 114 (2018) 245-258.
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| • |
Loukusa, H., Ikonen, T., Valtavirta, V. and Tulkki, V. (2016)
"Thermochemical modeling of nuclear fuel and the effects of oxygen potential buffers."
J. Nucl. Mat., 481 (2016) 101-110.
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| • |
Lovecký, M., Piterka, L., Prehradný, J. and Škoda, R. (2014)
" UWB1 – Fast nuclear fuel depletion code."
Ann. Nucl. Energy, 71 (2014) 333-339.
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| • |
Lovecký, M., Škoda, R., Hussein, M., Song, J. and Chan, P. (2015)
"Burnable Absorbers in CANDU Fuel Bundle Depletion with UWB1 Code."
In proc. 7ICMSNSE, Ottawa, ON, Oct. 18-21, 2015.
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| • |
Lovecký, M., Škoda, R., Hussein, M., Song, J. and Chan, P. (2017)
"The application of UWB1 nuclear fuel depletion code on a CANDU fuel bundle"
Prog. Nucl. Energy, 90 (2016) 127-139.
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| • |
Lu, C., Hiscox, B., Terrani, K. and Brown, N. (2018)
"Fully ceramic microencapsulated fuel in prismatic high temperature gas-cooled reactors: Analysis of reactor performance and safety characteristics."
Ann. Nucl. Energy, 2018 (114) 277-287.
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Lu, C. and Brown, N. (2018)
"Fully Ceramic Microencapsulated Fuel in Prismatic High Temperature Gas-Cooled Reactors: Impact on Control Rod Worth and Temperature Distribution in the Core."
Trans. Am. Nucl. Soc., 118 (2018) 1551-1554.
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Lu, C. and Brown, N. (2019)
"Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost."
Nucl. Eng. Design, 347 (2019) 108-121.
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Lu, Q. and Rizwan-uddin (2013)
"Stability analysis of a natural circulation lead-cooled fast reactor."
Trans. Am. Nucl. Soc., 109 (2013) 1723-1725.
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Lu, Y., Zhou, G., Hernandez, F., Pereslavtsev, P., Leppänen, J. and Ye, M. (2020)
"Benchmark of Serpent-2 with MCNP: Application to European DEMO HCPB breeding blanket."
Fusion Eng. Design, 155 (2020) 111583.
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Luciano, N., Ottinger, K., Collins, P., Gentry, C., George, N., Pawel, A., Kenner, K., Harty, S., Chvala, O., Maldonado, I. (2015)
"The Nestle 3D Nodal Core Simulator: Modern Reactor Models."
In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
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| • |
Luzzi, L., Cammi, A., Di Marcello, V., Lorenzi, S., Pizzocri, D. and Van Uffelen, P. (2014)
"Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor."
Nucl. Eng. Design, 277 (2014) 173-187.
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| • |
Lyons, J., Marcum, W., Morrell, S. and DeHart, M. (2015)
"Reactor Physics Scoping and Characterization Study on Implementation of TRIGA Fuel in the Advanced Test Reactor."
Nucl. Technol., 189 (2015) 202-217.
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Lötsch, T. (2014)
"Fuel assembly burnup calculations for VVER fuel assemblies with the MONTE CARLO code SERPENT."
Kerntechnik, 79 (2014) 295-302.
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| • |
Mahjoub, M. and Koclas, J. (2015)
"Comparative Static Simulations of a CANDU6 Cell Using Different Transport Codes."
In proc. 35th Annual Conference of the Canadian Nuclear Society, Saint John, New Brunswick, Canada, May 31 - Jun. 3, 2015.
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| • |
Maiorino, J., Stefani, G., Moreira, J., Rossi, P. and Santos, T. (2017)
"Feasibility to convert an advanced PWR from UO2 to a mixed U/ThO2 core – Part I: Parametric studies."
Ann. Nucl. Energy, 102 (2017) 47-55.
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| • |
Mantout, A. Seubert, A. and Velkov, K. (2017)
"Time-Dependent External Distributed Neutron Source Capability in PARCS and Comparison with TORT-TD."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Margulis, M. and Shwageraus, E. (2014)
"Conceptual Design of a Self-Sustainable Pressurized Water Reactor with Boiling Channels."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Margulis, M. and Shwageraus, E. (2015)
"High conversion pressurized water reactor with boiling channels."
Nucl. Eng. Design, 292 (2015) 98-111.
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| • |
Margulis, M., Gilad, E. and Blaise. P. (2016a)
"Monte Carlo Analysis of SNEAK-12A Core Disruption in Liquid-metal Fast Breeder Reactors - The Path for Innovative Severe Accident Studies in ZPR."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Margulis, M. and Gilad, E. (2016b)
"Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system."
Prog. Nucl. Energy, 88 (2016) 118-133.
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| • |
Margulis, M. and Gilad, E. (2016c)
"Development and Verification of the Dynamic System Code THERMO-T for Research Reactor Accident Analysis."
Nucl. Technol., 196 (2016) 377-395.
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Margulis, M., Blaise, P., Gabrielli, F., Gruel, A., Mellier, F. and Gilad, E. (2017a)
"The path for innovative severe accident neutronics studies in ZPRs. Part I.1 - Analysis of SNEAK-12A experiments for core disruption in LMFBRs."
Prog. Nucl. Energy, 94 (2017) 106-125.
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| • |
Margulis, M., Blaise, P., Mellier, F. and Gilad, E. (2017b)
"The path for innovative severe accident neutronics studies in ZPRs. part I.2 - Interpretation of SNEAK-12A experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients."
Prog. Nucl. Energy, 96 (2017) 97-117.
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Margulis, M., Blaise, P., Buiron, L. and Gilad, E. (2017c)
"ZPR Core Representativity of SFR Reactivity Effects During Core Meltdown."
Trans. Am. Nucl. Soc., 117 (2017) 1503-1506.
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| • |
Margulis, M., Blaise, P., Mellier, F. and Gilad, E. (2018a)
"The path for innovative severe accident neutronics studies in ZPRs. Part II.2 - Interpretation of SNEAK-12B experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients."
Prog. Nucl. Energy, 105 (2018) 124-135.
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| • |
Margulis, M. and Gilad, E. (2018b)
"Simulations of SPERT-IV D12/15 transient experiments using the system code THERMO-T."
Prog. Nucl. Energy, 109 (2018) 1-11.
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Margulis, M., Blaise, and Gilad, E. (2019a)
"Modeling representative Gen-IV molten fuel reactivity effects in the ZEPHYR ZPR - LFR analysis."
Int. J. Energy Res., 43 (2019) 829–843.
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| • |
Margulis, M., Blaise, P., Gabrielli, F., Gruel, A., Mellier, F. and Gilad, E. (2019b)
"The path for innovative severe accident neutronics studies in ZPRs – Analysis of SNEAK-12B experiments for core disruption in LMFBRs."
Ann. Nucl. Energy, 124 (2019) 119-131.
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Martin. N. and Hébert A. (2010)
"An Investigation on the Use Of Probability Table Cross-sections in Monte Carlo Lattice Calculations."
In proc. PHYSOR 2010, Pittsburgh, PA, May 9-14, 2010.
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| • |
Martin, N. and Hebert, A.
"A Monte Carlo Lattice Code with Probability Tables and Optimized Energy Meshes."
Nucl. Sci. Eng., 167 (2011) 177-195.
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| • |
Martinez, J., Cabellos, O., Diez, C., Gilfillan, F. and Barbas, A. (2011)
"Isotopic prediction calculation methodologies: Application to Vandellos-II reactor cycles 7-11."
In proc. M&C 2011, Rio de Janeiro, Brazil, May 8-12, 2011.
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| • |
Mascolino, V., Roskoff, N. and Haghighat, A. (2018)
"Benchmarking of the Rapid Code System Using the CBC-32 Cask With Variable Burnups."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Mascolino, V., Pungercic, A., Haghighat A., and Snoj, L. (2019a)
"Experimental and Computational Benchmarking of RAPID Using the JSI TRIGA Mark-II Reactor."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Mascolino, V. and Haghighat, A. (2019b)
"Validation of the Transient Fission Matrix Code tRAPID Against the Flattop-Pu Benchmark."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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Mascolino, V., Haghighat, A., Polys, N., Wang, M. and Rajamohan, S. (2019c)
"A Collaborative Virtual Reality System (VRS) with X3D Visualization for RAPID."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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Maul, L., Braoudakis, G., Ho, M. and Yeoh G. (2016)
"OPAL Reactor Calculations Using Reactor Physics Code Serpent."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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Maul, L., Shen, D. and Fratoni, M.(2016)
"Neutronics Code Benchmark for Fluoride-Salt-Cooled Reactors."
Trans. Am. Nucl. Soc., 115 (2016) 1169-1172.
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Maul, L. (2017)
"Impact of Perturbed H2O Thermal Scattering Data in OPAL Reactor Calculations."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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Maul, L. (2018)
"Impact of new nuclear data on neutronic calculations of the OPAL Reactor using Serpent."
Ann. Nucl. Energy, 115 (2018) 523-533.
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McMurray, J., Lindemer, T., Brown, N., Reif, T., Morris, R. and J. Hunn J. (2017)
"Determining the minimum required uranium carbide content for HTGR UCO fuel kernels."
Ann. Nucl. Energy, 104 (2017) 237-242.
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Mehta, V. and Kotlyar, D. (2017a)
"Use of Spectral Shift to Greatly Improve Uranium Utilization in FHR Designs."
Trans. Am. Nucl. Soc., 116 (2017) 1203-1206.
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Mehta, V. and Kotlyar, D. (2017b)
"Spectral Shift Operation with Multi-Reloading Scheme Analysis in the SmAHTR Design."
Trans. Am. Nucl. Soc., 117 (2017) 1335-1338.
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Mehta, V. and Kotlyar, D. (2019)
"Core Analysis of spectral shift operated SmAHTR."
Ann. Nucl. Energy, 123 (2019) 46-58.
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Mercatali, L., Venturini, A., Daeubler, M. and Sanchez, V. (2015)
"SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark."
Ann. Nucl. Energy, 83 (2015) 328-341.
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Merk, B., Glivici-Cotruta, V., Duerigen, S., Rohde, U. and Kliem, S. (2013)
"Overview of major HZDR developments for fast reactor analysis."
Nucl. Eng. Design, 265 (2013) 1194-1204.
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Mickus, I. and Dufek, J. (2018)
"Optimal neutron population growth in accelerated Monte Carlo criticality calculations."
Ann. Nucl. Energy, 117 (2018) 297-304.
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Mickus, I., Dufek, J. and Tuttelberg, K. (2015)
"Performance of the Explicit Euler and Predictor-Corrector-Based Coupling Schemes in Monte Carlo Burnup Calculations of Fast Reactors."
Nucl. Technol., 191 (2015) 193-198.
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Miglierini, B. and Kozlowski, T. (2018)
"Investigation of VVER-1000 rod ejection accident according to the Phenomenon Identification and Ranking Tables for PWR."
Prog. Nucl. Energy, 108 (2018) 438-444.
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Milany, S. and Marleau, G. (2017)
"A Hybrid Stochastic Deterministic Approach for Full Core Neutronics."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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Mohamed, A., Gentry, C., Godfrey, A. and Franceschini, F. (2018)
"VERA MPACT Depletion Validation for a Variety of PWR Fuel Types and Burnable Absorbers."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Mohamed, H., Kotlyar, D., Parks, G. and Shaposhnik, Y. (2016a)
"Coupled Neutronic-thermal-hydraylic Analysis of a Small FHR Core with Pin-type Fuel Assemblies."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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Mohamed, H., Lindley, B., Parks, G. and Leppänen, J. (2016b)
"Neutronic Assessment of TRISO Particle Fuels in a Small Fluoride Salt-cooled High-temperature Reactor."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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Moser, D., Wheeler, A. and Chvala, O. (2017)
"Lattice optimization for graphite moderated molten salt reactors using low-enriched uranium fuel."
Ann. Nucl. Energy, 110 (2017) 1-10.
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Motalab, M., Hartanto, D. and Kim, Y. (2014a)
"Detailed Monte Carlo Evaluation of the Power Coefficient of
Reactivity of CANDU Reactor."
Trans. Korean Nucl. Soc., Spring Meeting, Jeju, Korea, May 29-30, 2014.
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Motalab, M., Kim, W. and Kim, Y. (2014b)
"Investigation of CANDU6 PCR with Detailed 3-D Monte Carlo Analysis."
In proc. PHWR Safety 2014/CANSAS-2014, Ottawa, ON, Canada, Jun. 23-26, 2014.
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Motalab, M., Cho, B., Kim, W., Cho, N. and Kim Y. (2015)
"Serpent-COREDAX Analysis of CANDU-6 Time-Average Model."
In proc. 7ICMSNSE, Ottawa, ON, Oct. 18-21, 2015.
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Motalab, M., Kim, W. and Kim, Y. (2018)
"Use of Er Burnable Absorber for Improvement of CANDU6 Safety Parameters."
Nucl. Technol., 201 (2018) 122-137.
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Motalab, M., Kim, W. and Kim., Y. (2018)
"Application of APEC Method in CANDU Analysis."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Mukin, E., Puragliesi, E., Pecchia, M. and Seidl, M. (2018)
"Subchannel modeling of single rod bowing in a bundle geometry."
Nucl. Eng. Design, 340 (2018) 347-369
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Muniz, R. dos Santos, A., Yamaguchi, M., Rossi, P., Domingos, D., Mura, L. and Silva, A. (2016)
"Neutronic analysis of a U–Mo–Al fuel and europium as burnable poison."
Ann. Nucl. Energy, 92 (2016) 46-51.
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Naceur, A. and Marleau, G. (2018)
"Neutronic analysis for accident tolerant cladding candidates in CANDU-6 reactors."
Ann. Nucl. Energy, 113 (2018) 147-161.
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Nam, S., Venneri, P., Kim, Y., Lee, J., Chang, s. and Jeong y. (2015)
"Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor."
Nucl. Eng. Techol., 47 (2015) 678-699.
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Navarro, J. and DeHart, M. (2015)
"Criticality Benchmarks for Validation of SERPENT as an ATR-LEU Conversion Reactor Physics Tool."
Trans. Am. Nucl. Soc., 113 (2015) 1070-1074.
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Nguyen, T., Wilkin, G. and Atfield, J. (2013)
"Monte Carlo calculations applied to Slowpoke full-reactor analysis."
CNL Nuclear Review, 2012, 43-46.
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Nguyen, X. and Kim, Y. (2016)
"A Study on Reconstruction of Intra-Pin Information in Pin-Wise Reactor Analysis."
Trans. Am. Nucl. Soc., 115 (2016) 1256-1259.
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Nguyen, X., Rahman, A. and Kim, Y. (2018a)
"Concepts and Characteristics of a Soluble-Boron-Free Small Modular Reactor with Centrally-Shielded Burnable Absorbers."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Nguyen, X., Yu, H. and Kim, Y. (2018b)
"Neutronic Optimization of the Reflector for a Soluble-Boron-Free Small Modular Reactor ATOM."
Trans. Am. Nucl. Soc., 119 (2018) 1167-1170.
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Nguyen, X. and Kim, Y. (2018c)
"A Study on Reconstruction of Intrapin Power Distribution in Pinwise Two-Group Diffusion Analysis."
Nucl. Sci. Eng., 189 (2018) 224-242.
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Nigg, D., LaPorta, A., Nielsen, J., Parry, J., DeHart, M., Bays, S. and Skerjanc, W. (2013)
"A Complex-geometry validation experiment for advanced neutron transport codes."
Trans. Am. Nucl. Soc., 109 (2013) 1490-1493.
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| • |
Nikitin, E., Fridman, E. and Mikityuk, K. (2015a)
"Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems."
Ann. Nucl. Energy, 74 (2015) 492-497.
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| • |
Nikitin, E., Fridman, E. and Mikityuk, K. (2015b)
"On the use of the SPH method in nodal diffusion analyses of SFR cores."
Ann. Nucl. Energy, 85 (2015) 544-551.
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| • |
Nikitin E. and Fridman, E. (2016)
"Axial Fuel Rod Expansion Model in Nodal Code DYN3D for SFR Application."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Nikitin, E., Fridman, E., Bilodid, Y. and Kliem, S. (2017)
"New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses."
Kerntechnik, 82 (2017) 284-288.
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| • |
Nikitin, E. and Fridman, E. (2019a)
"Application of the Coordinate Transformation in Nodal Diffusion Calculations of Radially Expanding SFR Cores."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Nikitin, E. and Fridman, E. (2019b)
"Modeling of the FFTF isothermal physics tests with the Serpent and DYN3D codes."
Ann. Nucl. Energy, 132 (2019) 679-685.
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| • |
Noguere, G., Scotta, J., De Saint Jean, C. and Archier P. (2017)
"Covariance matrices of the hydrogen neutron cross sections bound in light water for the JEFF-3.1.1 neutron library."
Ann. Nucl. Energy, 104 (2017) 132-145.
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| • |
Noh, K., Jung, K., Tak, T. and Lee, D. (2014)
"BEAVRS Whole Core Benchmark Analysis Using Monte Carlo Codes."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Novak, O. and Chvala, O. (2016)
"Lessons Learned from a VVER Benchmark Modeling."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Novak, O., Chvala, O., Lociano, N. and Maldonado, I. (2017)
"VVER 1000 Khmelnitskiy benchmark analysis calculated by Serpent2."
Ann. Nucl. Energy, 110 (2017) 948-957.
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| • |
Novak, O., Sklenka, L., Huml, O., Frybort, J., Chvala, O., Luciano, N. and Maldonado, I. (2019)
"Benchmark evaluation of zero-power critical parameters for the Temelin VVER nuclear reactor using SERPENT & NESTLE and MCNP."
Nucl. Eng. Design, 353 (2019) 110243.
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Ochoa, R., Jimeneza, G. and Perez-Martin, S. (2013a)
"Analysis of a Spanish energy scenario with generation IV nuclear reactors."
Energy Conversion and Management, 75 (2013) 389-397.
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Ochoa, R., Vázquez, M., Álvarez Velarde, F., Martín-Fuertes, F., García-Herranz, N. and Cuervo, D. (2013b)
"A comparative study of Monte Carlo-coupled depletion codes applied to a sodium fast reactor design loaded with minor actinides."
Ann. Nucl. Energy, 57 (2013) 32-40.
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Ortensi, J., Cogliati, J., Pope, M. and Bess, J. (2010a)
"Deterministic modeling of the high temperature test reactor with DRAGON-HEXPEDITE."
In proc. HTR 2010, Prague, Czech Republic, Oct. 18-20, 2010.
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Ortensi, J., Cogliati, J., Pope, M., Bess, J., Ferrer, R., Bingham, A. and Ougouag, A. (2010b)
"Deterministic modeling of the High Temperature Test Reactor."
INL/EXT-10-18969, Idaho National Laboratory, 2010.
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Ortensi, J., Wang, Y., Baker, B., Schunert, S., Gleicher F., DeHart, M., Laurier, A. and Hébert, A. (2016a)
"Preparation of a Neutron Transport Data Set for Simulations of the Transient Test Reactor Facility."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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Ortensi, J., Schunert, S., Wang, Y., Baker, B., Gleicher, F. and DeHart M. (2016b)
"A Neutron Streaming Problem to Test Rattlesnake Methods for TREAT."
Trans. Am. Nucl. Soc., 115 (2016) 1389-1392.
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Ortensi, J., Wang, Y., Laurier, A., Schunert, S., Hébert, A. and DeHart, M. (2018a)
"A Newton solution for the Superhomogenization method: The PJFNK-SPH."
Ann. Nucl. Energy, 111 (2018) 579-594.
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Ortensi, J., Schunert, S. Wang, Y., Labouré, V., Gleicher, F. and Martineau, R. (2018b)
"Analysis of the HTR-10 Initial Critical Core with the MAMMOTH Reactor Physics Application."
Trans. Am. Nucl. Soc., 119 (2018) 1103-1107.
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Osborne, A., Deinert, M. (2014)
"Using Spectral Shift to Reduce Radiation Damage in Breed-Burn Reactors."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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Ouisloumen, M. (2017)
"PARAGON2 Depletion Validation Using SERPENT2 Monte Carlo Code."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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Ouisloumen, M. (2018)
"Validation of PARAGON2 for PWR Assemblies with High Enrichments1."
Trans. Am. Nucl. Soc., 119 (2018) 1203-1206.
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Palmiotti, G., Salvatores, M., Sen, S., Rabiti, C., Aufiero, M. and Tommasi, J. (2018)
"Investigating Decoupling Effects in CFV Type of Reactors Using Avery’s Coupled Reactor Theory."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Papadionysiou, M., Seongchan, K., Hursin, M., Vasiliev, A., Ferroukhi, H., Pautz, A., Gyu Joo, H. (2019)
"Assessment of nTRACER and PARCS Performance for VVER Configurations."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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Park, H., Saller, T., Seker, V. and Downar, T. (2013)
"Neutronics analysis of the high temperature engineering test reactor (HTTR)."
Trans. Am. Nucl. Soc., 108 (2013) 799-802.
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Park, Y., Swenson, A., Wilson, P., Cheng, Y., Reed, R. and Roberts, J. (2018)
"Improved Modeling of the University of Wisconsin Nuclear Reactor by Automatic Generation of Computational Models."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Pataki, I., Batki, B., Kereszturi, A. and Panka, I. (2018)
"Application of discontinuity factors and group constants generated by SERPENT in the KIKO3 DMG code."
Kerntechnik, 83 (2018) 275-281.
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Patel, V. and Tsvetkov, P. (2012)
"Integrated multi-modular fast reactor concept design."
In proc. ICONE20, Anaheim, CA, Jul. 30 - Aug. 3, 2012.
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Patel, V. and Tsvetkov, P. (2013a)
"Concept of a high temperature integrated multi-modular thermal reactor."
Ann. Nucl. Energy, 55 (2013) 312-321.
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Patel, V. and Tsvetkov, P. (2013b)
"Multi-module approach to modularity in a neutronically coupled high temperature multi-modular system."
Nucl. Eng. Design, 263 (2013) 411-418.
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Patel, V., Eades, M. and Venneri, P. (2018)
"Does Xe-135m Cross-Section Uncertainty Matter in Nuclear Thermal Propulsion Reactors?."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Pecchia, M., Wicaksono, D., Grimm, P., Vasilieva, A., Perret, G., Ferroukhi, H and Pautza, A. (2016)
"Validation of Monte Carlo based burnup codes against LWR-PROTEUS Phase-II experimental data."
Ann. Nucl. Energy, 97 (2016) 153-164.
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Pecchia, M., Ferroukhi, H., Vasiliev, A. and Grimm, P. (2019)
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Ann. Nucl. Energy, 129 (2019) 67-78.
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Pereira, G, Johnson, A. E., Bilodid, Y., Fridman, E. and Kotlyar, D. (2019)
"Applying the Serpent-DYN3D code sequence for the decay heat analysis of metallic fuel sodium fast reactor."
Ann. Nucl. Energy, 125 (2019) 291-306.
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Perko, Z., Pelloni, S., Mikityuk, K., Krepel, J., Szieberth, M., Gaëtan, G., Vrban, B., Lüley, J., Cerba, S., Halasz, M., Feher, S., Reiss, T., Kloosterman, J., Stainsby, R. and Poette, G. (2015)
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Pettersen, E. and Mikityuk, K. (2017)
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Ponomarev, A., Bednarova, A. and Mikityuk, K. (2018)
"New Sodium Fast Reactor Neutronics Benchmark."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Pope, M., Gougar, H. and Ryskamp, J. (2014)
"Design Studies for a Multiple Application Thermal Reactor for Irradiation Experiments (MATRIX)."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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Portinari, D., Aufiero, M., Calzavara Y., Cammi, A., Lorenzi S., Bidaud, A. (2019)
"Safety Parameters Uncertainty and Sensitivity Analysis for High Flux Reactor at Institut Laue Langevin."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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Prévot, P., Nuttin, A., Capellan, N. and Méplan, C. (2017)
"Enhancements to the Nodal Drift Method for a Rod Ejection Accident in a PWR-like mini-core with lumped thermal mode."
Ann. Nucl. Energy, 101 (2017) 128-138.
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Prinsloo, R., Zamonsky, O., Tomasevic, D., Erasmus, B. and Groenewald, S. (2015)
"A Semi-Heterogeneous Method for On-the-fly Environmental Correction of Nodal Equivalence Parameters."
In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
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Pungercic, A., Calic, D. and Snoj, L. (2019)
"STRIGA: A Computer Tool for TRIGA Reactor Burnup Calculations."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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Qasim Awan, M., Cao, L., Wu, H., Shen, W. and Li, Z. (2018)
"Neutronic design study of a small modular IPWR loaded with accident tolerant-fully ceramic micro-encapsulated (AT-FCM) fuel."
Nucl. Eng. Design, 335 (2018) 18-29
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Qiu, Y., Aufiero, M., Wang, K. and Fratoni, M. (2016)
"Development of sensitivity analysis capabilities of generalized responses to nuclear data in Monte Carlo code RMC."
Ann. Nucl. Energy, 97 (2016) 142-152.
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Qvist, S. and Greenspan, E. (2012)
"Inherent safety of minimum burnup breed-and-burn reactors."
In proc. ICAPP 2012, Chicago, IL, Jun. 24-28, 2012.
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"Automated breed-and-burn core design using the ADOPT code."
In proc. ICAPP 2013, Jeju, Korea, Apr. 14-18, 2013.
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Qvist, S. and Greenspan, E. (2014a)
"The ADOPT code for automated fast reactor core design."
Ann. Nucl. Energy, 71 (2014) 23–36.
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Qvist, S. and Greenspan, E. (2014b)
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Prog. Nucl. Energy, 77 (2014) 32–47.
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Qvist, S. and Greenspan, E. (2014c)
"3D Shuffling in Breed and Burn Reactors."
Trans. Am. Nucl. Soc., 111 (2014) 1274-1277.
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Qvist, S., Hou, J. and Greenspan, E. (2015)
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Ann. Nucl. Energy, 85 (2015) 93-114.
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Qvist, S., Hellesen, C., Thiele, R., Dubberley, A., Gradecka, M. and Greenspan, E. (2016)
"Autonomous Reactivity Control (ARC) — Principles, geometry and design process."
Nucl. Eng. Design, 307 (2016) 249-274.
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Qvist, S., Hellesen, C., Gradecka, M., Dubberley, A., Fanning, T., Greenspan, E. (2017)
"Tailoring the response of Autonomous Reactivity Control (ARC) systems."
Ann. Nucl. Energy, 99 (2017) 383-398.
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Rachamin, R. and Fridman, E. (2012)
"Conceptual Design of a Pressure Tube Light Water Reactor with Variable Moderator Control."
In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
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Rachamin, R., Wemple, C. and Fridman, E. (2013)
"Neutronic analysis of SFR core with HELIOS-2, Serpent, and DYN3D codes."
Ann. Nucl. Energy, 55 (2013) 194-204.
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Rachamin, R. and Kliem, S. (2017a)
"Validation of the DYN3D-Serpent code system for SFR cores using selected BFS experiments. Part I: Serpent calculations."
Ann. Nucl. Energy, 102 (2017) 158-167.
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Rachamin, R. and Kliem, S. (2017b)
"Application of SPH Method for Sodium Fast Reactor Analysis."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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Rachamin, R. and Kliem, S. (2018)
"Validation of the DYN3D-Serpent code system for SFR cores using selected BFS experiments. Part II: DYN3D calculations."
Ann. Nucl. Energy, 114 (2018) 181-190.
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Radaideh, M., Price, D., O'Grady, D. and Kozlowski, T. (2019)
"Advanced BWR criticality safety part I: Model development, model benchmarking, and depletion with uncertainty analysis."
Prog. Nucl. Energy, 113 (2019) 230-246.
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Rais, A., Siefman, D., Girardin, G., Hursin, M. and Pautz, A. (2015)
"Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL."
Sci. Technol. Nucl. Install., 2015 (2015), Article ID 237646.
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Rais, A., Hursin, M., Perret G. and Pautz, A. (2016)
"Experimental Validation of Control Rod Reactivity Worth and Fission Rate Distributions for the CROCUS Reactor."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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Rais, A., Siefman, D., Hursin, M., Ward, A. and Pautz, A. (2017)
"Neutronics modeling of the CROCUS reactor with SERPENT and PARCS codes."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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Ramey, K and Petrovic, B. (2015a)
"Power Density Uncertainties in 2D Full Core Serpent Simulations."
Trans. Am. Nucl. Soc., 113 (2015) 1223-1224.
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Ramey, K and Petrovic, B. (2015b)
"2D Serpent Model for I2S-LWR Radial Reflector Studies."
Trans. Am. Nucl. Soc., 113 (2015) 1225-1227.
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Ramey, K. and Petrovic, B. (2017)
"Numerical Artifacts in On-the-Fly Doppler Broadening Near Reference Temperatures."
Trans. Am. Nucl. Soc., 117 (2017) 1262-1265.
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Ramey, K. and Petrovic, B. (2018)
"Monte Carlo modeling and simulations of AHTR fuel assembly to support V&V of FHR core physics methods."
Ann. Nucl. Energy, 118 (2018) 272-282.
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Rantamäki, K., Häkkinen, S. and Anttila, M. (2011)
"Impact of cross section libraries on CASMO-4E and CASMO-4 results."
Ann. Nucl. Energy, 38 (2011) 2830-2835.
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"Monte Carlo Simulation of Inclined Reactivity Control Rod and Boron Poisoning for the Canadian-SCWR Supercell;."
ASME J. of Nuclear Rad Sci., 2 (2016) 021015.
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Rau, A., He, D. and Walters, W. (2018)
"Application of Fission Matrix Correction Method to TRIGA Reactor Core."
Trans. Am. Nucl. Soc., 118 (2018) 1014-1017.
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Rau, A. and Walters, W. (2019)
"Fission Matrix Methods for Nuclear Thermal Propulsion Applications."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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Rawlins, S. and Kim, Y. (2018a)
"Feasibility of Low Thrust, Low-Enriched Uranium Nuclear Thermal Propulsion."
In proc. NETS 2018, Las Vegas, NV, Feb. 26 - Mar. 1, 2018.
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Rawlins, S. and Kim, Y. (2018b)
"Low-Thrust, Low-Enriched Uranium Nuclear Thermal Propulsion."
In proc. NURER 2018, Jeju, Korea, Sept. 30 - Oct. 03, 2018.
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Read, E. (2010)
"Methodology and Visualization of Monte Carlo calculation for displacements per atom in light water reactors."
In proc. SNA + MC 2010, Tokyo, Japan, Oct. 17-21, 2010.
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Read, N. and Shwageraus, E. (2018)
"Maximising Specific Power of Low Enriched Uranium Reactor for Electric Space Propulsion."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Reed, R. and Roberts, J. (2019)
"Effectiveness of the discrete generalized multigroup method based on truncated, POD-driven basis sets."
Ann. Nucl. Energy, 126 (2019) 253-261.
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Rehak, J., Kerby, L., DeHart, M. and Slaybaugh, R. (2019)
"Weighted delta-tracking in scattering media."
Nucl. Eng. Design, 342 (2019) 231-239
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Reinaldo, Y. and Francois, J. (2018)
"Analysis of the Use of Thorium Fuel in the European 2400 MWth Gas-Cooled Fast Reactor."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Reiter, C., Breitkreutz, H., Röhrmoser, A. and Petry, W. (2016)
"First steps towards a coupled code system for transient calculations for FRM II."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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Reiter, C., Breitkreutz, H., Öhrmoser, A., Seubert, A. and Petry, W. (2018)
"High Precision Neutronic Calculations for Transient Simulations for FRM II."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Reiter, C., Breitkreutz, H., Röhrmoser, A., Seubert, A. and Petry, W. (2019)
"Neutronic simulations for the FRM II."
Ann. Nucl. Energy, 131 (2019) 1-8.
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Reiter, C., Breitkreutz, H., Röhrmoser, A., Seubert, A. and Petry, W. (2019)
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Ann. Nucl. Energy, 131 (2019) 1-8.
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Reitsma, F. and Kim, W. (2016)
"The Contribution of Cross-section Uncertainties to Pebble Bed Reactor Eigenvalues Results: IAEA Cooperative Research Project Phase I Standalone Neutronics."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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Restani, R., Horvath, M., Goll, W., Bertsch, J., Gavillet, D., Hermann, A., Martin, M. and Walker, C. T. (2016)
"On the condition of UO2 nuclear fuel irradiated in a PWR to a burn-up in excess of 110 MWd/kgHM."
J. Nucl. Mat., 481 (2016) 88-100.
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Reyes, G., Escamilla, S., Gómez Torres, A. and del Valle Gallegos, E. (2018)
"Gemma: Development of a two-dimensional neutron transport code with the method of characteristics."
Ann. Nucl. Energy, 115 (2018) 367-376.
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Richard, J., Forget, B., Forsberg, C. and Smith, K. (2015)
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Trans. Am. Nucl. Soc., 113 (2015) 937-942.
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Rider, T., Osborne, A. and Deinert, M. (2018)
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Trans. Am. Nucl. Soc., 119 (2018) 205-208.
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Rintala, L., Aarnio, P., Clerc, S. and Salomaa, R. (2012)
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In proc. 21st International Conference Nuclear Energy for New Europe 2012, Ljubljana, Slovenia, Sept. 5-7, 2012.
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Rintala, V., Suikkanen, H., Leppänen, J. and Kyrki-Rajamäki, R. (2015)
"Modeling of realistic pebble bed reactor geometries using the Serpent Monte Carlo code."
Ann. Nucl. Energy, 77 (2015) 223-230.
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Rochman, D., Koning, A. and Da Cruz, D. (2012)
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Nucl. Technol., 179 (2012) 323-338.
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Nucl. Sci. Eng., 177 (2014) 337-349.
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Nucl. Data Sheets, 139 (2017) 1-76.
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Prog. Nucl. Energy, 88 (2016) 170-190.
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Romojaro, P., Álvarez-Velarde, F. and García-Herranz, N. (2018)
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In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Romojaro, P., Alvarez-Velarde, F. and García-Herranz, N. (2019)
"Sensitivity methods for effective delayed neutron fraction and neutron generation time with summon."
Ann. Nucl. Energy, 126 (2019) 410-418.
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Roskoff, N. and Haghighat, A. (2018)
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In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Routsonis, K., Blaise, P., Tommasi, J. and Valocchi, G. (2019)
"Transient Fission Matrix Analysis of Rod Drop Experiments in Coupled Cores for Addressing High Dominance Ratio Configurations."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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Rouxelin, P., Strydom, G. and Ivanov, K. (2017)
"IAEA CRP on HTGR Uncertainties: Quantification of Nuclide Inventory Uncertainties in Depletion Calculations."
Trans. Am. Nucl. Soc., 117 (2017) 1397-1400.
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Rouxelin, P., Styrdom, G., Alfonsi, A. and Ivanov, K. (2018)
"The IAEA CRP on HTGR uncertainties: Sensitivity study of PHISICS/RELAP5-3D MHTGR-350 core calculations using various SCALE/NEWT cross-section sets for Ex. II-1a."
Nucl. Eng. Design, 329 (2018) 156-166.
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Rowland, K. Bergmann, R. Slaybaugh, R. and Vujic, J. (2017)
"Delta-tracking in the GPU-accelerated WARP Monte Carlo Neutron Transport Code."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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Rykhlevskii, A., Lindsay, A. and Huff, K. (2017a)
"Online Reprocessing Simulation for Thorium-Fueled Molten Salt Breeder Reactor."
Trans. Am. Nucl. Soc., 117 (2017) 239-242.
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Rykhlevskii, A., Lindsay, A. and Huff, K. (2017b)
"Full-Core Analysis of Thorium-Fueled Molten Salt Breeder Reactor Using the SERPENT 2 Monte Carlo Code."
Trans. Am. Nucl. Soc., 117 (2017) 1343-1346.
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Rykhlevskii, A., Whan Bae, J. and Huff, K. (2019a)
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Ann. Nucl. Energy, 128 (2019) 366-379.
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| • |
Rykhlevskii, A., Betzler, B., Worrall, A. and Huff, K. (2019b)
"Fuel Cycle Performance of Fast Spectrum Molten Salt Reactor Designs."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Sahlberg, V. (2016b)
"Recalculating the steady state conditions of the V-1000 zero-power facility at Kurchatov Institute using Monte Carlo and nodal diffusion."
In proc. 26th AER Symposium on VVER Reactor Physics and reactor safety, Helsinki, Finland, Oct. 10-14, 2016.
|
| • |
Sahlberg, V. (2017)
"Calculating V-1000 Core Model With Serpent 2 - HEXTRAN Code Sequence."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Sahlberg, V. (2017)
"Recalculating the steady state conditions of the V-1000 zero-power facility at Kurchatov Institute using Monte Carlo and nodal diffusion codes."
Kerntechnik, 82 (2018) 420-425.
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| • |
Saracco, P., Chentre, N., Abrate, N., Dulla, S. and P. Ravetto, (2019)
"Neutron multiplication and fissile material distribution in a nuclear reactor."
Ann. Nucl. Energy, 133 (2019) 696-706.
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| • |
Sartori, A., Baroli, D., Cammi, A., Chiesa, D., Luzzi, L., Ponciroli, R., Previtali, E. Ricotti, M., Rozza, G. and Sisti, M. (2014)
"Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics."
Ann. Nucl. Energy, 71 (2014) 217-229.
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| • |
Sartori, A., Cammi, A., Luzzi, L. and Rozza, G. (2016)
"A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel."
Ann. Nucl. Energy, 87 (2016) 198-208.
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| • |
Scarfò, D., Caiffi, B., Chersola, D. and Lomonaco, G. (2015)
"A Preliminary Assessment of the Transmutation Potentialities for an ITER-like FW Sector Loaded with MA."
Global Journal of Energy Technology Research Update, 2 (2015) 52-64.
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| • |
Scherr, J. and Tsvetkov, P. (2015)
"Fast Spectrum Material’s Testing Reactor with Variable Energy Spectra to Support Advanced Reactors Program and Light Water Reactor Sustainability Program R&D."
Trans. Am. Nucl. Soc., 113 (2015) 1115-1118.
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| • |
Scherr, J. and Tsvetkov, P. (2016)
"Fast Spectrum Materials Test Reactor with Variable Neutron Spectra in Support of Next Generation Nuclear Power Plant and Light Water Reactor Sustainability R&D."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Scherr, J. and Tsvetkov, P. (2018)
"Reactor design strategy to support spectral variability within a sodium-cooled fast spectrum materials testing reactor."
Ann. Nucl. Energy, 113 (2018) 15-24.
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| • |
Schwanke, P., Liu, Q and Nichita, E. (2017)
"A Multi-Purpose Homogeneous-Node Benchmark for PHWR Configurations"
Trans. Am. Nucl. Soc., 117 (2017) 1296-1300.
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| • |
Scopatz, A., Romano, P., Wilson, P. and Huff, K. (2012)
"PYNE : Python for Nuclear Engineering."
Trans. Am. Nucl. Soc., 107 (2012) 985-987.
|
| • |
Scopatz, A. and Schneider, E. (2012)
"Interpolations of nuclide-specific scattering kernels generated with Serpent."
In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
|
| • |
Seker, V., Neumann, M., Smith, H. and Downar, T. (2017)
"Calculation of TREAT Minimum Critical and M8CAL Core Benchmarks with SERPENT."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Sen, S., Youinou, G., Wigeland, R., Salvatores, M., Palmiotti, G., Hill, D., Henslee, P., Finck, P. and Davis, C. (2016)
"A Versatile Innovative Coupled Thermal-fast Test Reactor."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
|
| • |
Sevecek, M., Kuban, J., Valach, M. and Skoda, R (2018)
"Development of high thermal conductivity UO2–Th heterogeneous fuel."
Prog. Nucl. Energy, 108 (2018) 489-496.
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| • |
Shapiro, R., Younker, I. and Fratoni, M. (2013)
"Neutronic performance of accident tolerant fuels."
Trans. Am. Nucl. Soc., 109 (2013) 1351-1353.
|
| • |
Shapiro, R., Vincenzi, M. and Fratoni, M. (2014)
"Optimization of Fully Ceramic Micro-Encapsulated Fuel Assembly for PWR."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Shapiro, R. and Fratoni, M. (2016)
"Assembly Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel."
Nucl. Technol., 194 (2016) 15-27.
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| • |
Shen, D., Fratoni, M., Aufiero, M., Bidaud, A., Powers, J. and Ilas, G. (2017)
"Progress Towards a Molten Salt Reactor Experiment Benchmark Evaluation."
Trans. Am. Nucl. Soc., 117 (2017) 1359-1361.
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| • |
Shen, D., Fratoni, M., Aufiero, M., Bidaud, A., Powers, J. and Ilas, G. (2018)
"Zero-Power Criticality Benchmark Evaluation of the Molten Salt Reactor Experiment."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Shen, W. (2012a)
"Assessment of the traditional neutron-diffusion core-analysis method for the analysis of the super critical water reactor."
Ann. Nucl. Energy, 45 (2012) 1-7.
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| • |
Shen, W. (2012b)
"On the better performance of the coarse-mesh finite-difference method for CANDU-type reactors."
Ann. Nucl. Energy, 46 (2012) 169-178.
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| • |
Shen, W. (2012c)
"Evaluation of the adequacy of using few-group lattice-homogenized properties for the diffusion analysis of the super critical water reactor."
In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
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| • |
Shen, W. (2012d)
"Root-cause Analysis of the Better Performance of the Coarse-mesh Finite-difference Method for CANDU-type Reactors."
In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
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| • |
Shi, J., Aufiero, M. and Fratoni, M. (2018)
"Sensitivity and Uncertainty Analysis of the Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR)."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Shirvan K. And Kazimi M. (2012)
"Nuclear Design Behaviour of Helical Cruciform Fuel Rods."
In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
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| • |
Shwageraus, E. and Read, N. (2017)
"Investigating Diffusion Coefficient Anisotropy in Axially Heterogeneous High Conversion Water Reactors."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Siefman, D., Girardin, G., Raisa, A., Pautz, A. and Hursin, M. (2015)
"Full Core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor."
Ann. Nucl. Energy, 85 (2015) 434–443.
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| • |
Siefman, D., Hursin, M., Aufiero, M., Bidaud, A. and Pautz, A. (2018)
"Convergence Analysis and Criterion for Data Assimilation with Sensitivities from Monte Carlo Neutron Transport Codes."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Siefman, D., Hursin, M., Aufiero, M., Bidaud, A. and Pautz, A. (2020)
"On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients."
Ann. Nucl. Energy, 135 (2020) 106951.
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| • |
Silva Albarrán, L., del Valle Gallegos, E. and Gómez Torres, A. (2013)
"Serpent: Una alternativa para el análisis de celdas de combustible nuclear de un BWR."
In proc. XXIV Congreso Anual de la SNM, Queretaro, México,
Jun. 30 - Jul. 3, 2013 (in Spanish).
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| • |
Singh, G., Gorton, J., Schappel, D., Brown, N., Katoh, Y., Wirth, B. and Terrani, K. (2019)
"Deformation analysis of SiC-SiC channel box for BWR applications."
J. Nucl. Mat., 513 (2019) 71-85.
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| • |
Sjöstrand, H., Alhassan, E., Duan, J., Gustavsson, C., Koning, A., Pomp, S., Rochman, D. and Österlund, M. (2014)
"Propagation of nuclear data uncertainties for ELECTRA burn-up calculations."
Nucl. Data Sheets, 118 (2014) 527-530.
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| • |
Skoda, R., Jirickova, J., Lovecky, M. and Zavorka, J. (2018)
"RADEC - Radially and Axially Designed Cores for Pebble Bed Nuclear Reactor."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
|
| • |
Sorrel, N. and Hawari, A. (2017)
"Establishing a Serpent Model for TREAT Transient Analysis."
Trans. Am. Nucl. Soc., 117 (2017) 149-152.
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| • |
Sorrell, N. and Hawari, A. (2019)
"TREAT M2 experiment modeling for transient benchmark analysis."
Ann. Nucl. Energy, 128 (2019) 398-405.
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| • |
Stauff, N., Kim, T., Taiwo, T., Buiron, L., Rimpault, G., Yamaji, A., Gulliford, J., K. Lee, Y., Brun, E., Guilliard, N., Bernnat, W., Uematsu, M., Sugino, K., Kugo, T., Pataki, P., Keresztúri, A., Tóta, Á., Ponomarev, A., Messaoudi, N., Lin Tan, R. and Kozlowski, T. (2014)
"Evaluation of Medium 1000MWth Sodium-Cooled Fast Reactor OECD Neutronic Benchmarks."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Suikkanen, H., Rintala, V. and Kyrki-Rajamäki, R. (2010)
"An approach for detailed reactor physics modelling of randomly packed pebble beds."
In proc. HTR 2010, Prague, Czech Republic, Oct. 18-20, 2010.
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| • |
Suikkanen, H. and Rintala, V. (2019)
"Assessing the Performance of Functional Expansion Tallies in the Serpent 2 Monte Carlo Code."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Sun, K., Wilson, J., Hauptman, S., Ji, R., Dave, A., Zou, Y. and Hu, L. (2018)
"Neutronics modeling and analysis of the TMSR-SF1 fuel lattice and full core with explicit fuel particle distribution and random pebble loadings."
Prog. Nucl. Energy, 109 (2018) 171-179.
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| • |
Suvdantsetseg, E., Wallenius, J. and Bortot, S. (2012)
"Optimization of the reactivity control drum system of ELECTRA."
Nucl. Eng. Design, 252 (2012) 209-214.
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| • |
Suvdantsetseg, E. and Wallenius, J. (2014a)
"An assessment of prompt neutron reproduction time in a reflector dominated fast critical system: ELECTRA."
Ann. Nucl. Energy, 71 (2014) 159–165.
|
| • |
Talamo, A. and Gohar, Y. (2015)
"Monte Carlo Analyses of the Yalina Thermal Facility with Serpent Stereolithography Geometry Model."
In proc. AccApp ’15, Washington, DC, Nov. 10-13, 2015.
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| • |
Talamo, A., Gohar, Y., Zhong, Z., Sikorin, S., Mandzik, S., Polazau, S., Hryharovich, T. and Holubeva, I. (2016a)
"Serpent Stereolithography Modeling of the GIACINT Critical Assembly Experimental Facility."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Talamo, A., Gohar, Y. and Leppänen, J. (2016b)
"Mesh Adaptive Search Optimization in SERPENT2 Stereolithography Geometry."
Trans. Am. Nucl. Soc., 115 (2016) 1127-1129.
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| • |
Talamo, A., Gohar, Y. and Leppänen, J. (2017a)
"SERPENT Performance with Hybrid Combinatorial and Stereolithographic Geometry."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Talamo, A., Gohar, Y. Leppänen, J. and Valtavirta, V. (2017b)
"The Precursor-Based Delayed Neutrons Emission Model Applied to a Water Level Transient."
Trans. Am. Nucl. Soc., 117 (2017) 1290-1291.
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| • |
Talamo, A., Gohar, Y. and Leppänen, J. (2018)
"SERPENT validation and optimization with mesh adaptive search on stereolithography geometry models."
Ann. Nucl. Energy, 115 (2018) 619-632.
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| • |
Talamo, A., Gohar Y., Valtavirta, V., Leppänen J., Sikorin, S., Mandzik, S., Polazau, S. and Hryharovich, T. (2019)
"SERPENT Validation Using GIACINT Facility Experimental Data from a Control Rod Insertion Transient."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Talamo, A., Gohar, Y., Sikorin, S., Mandzik, S., Polazau, S., Hryharovich, T., Valtavirta, V. and Leppänen, J. (2019)
"Utilization of the Precursor-Based Delayed Neutrons Emission Model for a Control Rod Insertion Transient."
Trans. Am. Nucl. Soc., 120 (2019) 983-984
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Templeton, J., Ortega M. and de Oliveira, C. (2014)
"Three-Dimensional Modeling of the Physics of the Transient Reactor Test (TREAT) Facility."
Trans. Am. Nucl. Soc., 111 (2014) 1303-1305.
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| • |
Terlizzi S. and Kotlyar D. (2018)
"Non-Ideal Convergence of the Fission Matrix Fundamental Eigenpair In Monte-Carlo Calculations."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Terlizzi, S. and Kotlyar, D. (2019)
"Verification of the Fission Matrix Decomposition Method Against Two Axially Heterogeneous Problems."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Tesinsky, M., Zhang, Y. and Wallenius, J. (2012a)
"The impact of americium on the ULOF and UTOP transients of the European lead-cooled system (ELSY)."
Ann. Nucl. Energy, 47 (2012) 104-109.
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Tesinsky, M., Wallenius, J., Jolkkonen, M. and Zhang, Y. (2012b)
"The impact of americium on transients in the European lead-cooled system ELSY loaded with nitride fuel."
Ann. Nucl. Energy, 50 (2012) 50-62.
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| • |
Tijero Cavia, J., Schubert, A., Van Uffelen, P., Pöml, P., Breémier, S., Somers, J., Seidl, M. and Macián-Juan, R. (2018)
"The TRANSURANUS burn-up model for thorium fuels under LWR conditions."
Nucl. Eng. Design, 326 (2018) 311-319.
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| • |
Topham, T. and Walters, W. (2018)
"Temperature Feedback Using the Fission Matrix for a TRIGA Reactor."
Trans. Am. Nucl. Soc., 119 (2018) 1233-1235.
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Topham, T., Rau, A. and Walters, W. (2020)
"An iterative fission matrix scheme for calculating steady-state power and critical control rod position in a TRIGA reactor."
Ann. Nucl. Energy, 135 (2020) 106984.
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| • |
Trinh, K., Parks, G., Kotlyar, D. and Fiorina, C. (2016)
"Fuel Cycle Analysis of Multi-batch Operation of a Denatured Molten Salt Reactor."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Trottier, A., Pfeiffer, S., and Serghiuta, D. (2019)
"SERPENT-Based Few-Group Cross Section Data for NESTLE-C."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Turner, A., Burns. A., Colling, B. and Leppänen, J. (2018).
"Applications of Serpent 2 Monte Carlo Code to ITER Neutronics Analysis."
Fusion Sci. Technol., 74 (2018) 315-320.
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Usheva, K., Kuten, S., Khruschinsky, A. and Babichev, L. (2017)
"Features of the radial reflector simulation for generation of two-group XS's for the VVER reactor core in Serpent Monte Carlo code."
In proc. TopSafe 2017, Vienna, Austria, Feb. 12-16, 2017.
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Vanhanen, R. (2014)
"Uncertainty analysis of infinite homogeneous lead and sodium cooled fast reactors at beginning of life."
Nucl. Eng. Design, 283 (2015) 168-174.
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Vasconcelos, V., Santos, A., Campolina, D., Theler, G. and Pereira, C. (2018)
"Coupled unstructured fine-mesh neutronics and thermal-hydraulics methodology using open software: A proof-of-concept."
Ann. Nucl. Energy, 115 (2018) 173-185.
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Venneri, P., Nam, S. and Kim, Y. (2014)
"Neutronics Study of the KANUTER Space Propulsion Reactor."
Trans. Korean Nucl. Soc., Spring Meeting, Jeju, Korea, May 29-30, 2014.
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Venneri, P and Kim, Y. (2015)
"Extreme Performance Multibatch Research Reactor Based on Simple Plate Fuel."
Trans. Am. Nucl. Soc., 113 (2015) 1067-1069.
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Venneri, P., Eades M. and Kim, Y. (2017)
"Passive Reactivity Control of Nuclear Thermal Propulsion Reactors."
Nucl. Technol., 197 (2017) 64-74.
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Verma, V., Filliatre, P., Hellesen, C., Jacobsson Svärdb, S and Jammes, C. (2016)
"Neutron flux monitoring with in-vessel fission chambers to detect an inadvertent control rod withdrawal in a sodium-cooled fast reactor."
Ann. Nucl. Energy, 94 (2016) 487-493.
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Verma, V., Filliatre, P., Hellesen, C., Jacobsson Svärd, S. and Jammes, C. (2018)
"Neutron Flux Monitoring During Slow Transient Conditions in a Sodium-Cooled Fast Reactor."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Verma, V., Demazière, C., Vinai, P., Ricciardi, G. and Jacqmin, R. (2019)
"Assessment of the Neutron Noise Induced by Stationary Fuel Assembly Vibrations in a Light Water Reactor."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Visan, I. and Moise, A. (2019)
"Evaluation of the Th–U mixed oxide fuel neutronic characteristics in a CANDU 6® reactor."
Ann. Nucl. Energy, 129 (2019) 240-248.
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Wallenius, J. and Fokau, A. (2009)
"A low power fast reactor cooled by natural circulation of LBE."
In proc. Global 2009, Paris, France, Sept. 6-11, 2009.
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Wallenius, J., Suvdantsetseg, E. and Fokau, A. (2012)
"ELECTRA: European lead-cooled training reactor."
Nucl. Technol., 177 (2012) 303-313.
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Wallenius, J., Bortot, S. and Suvdantsetseg, E. (2013)
"ELECTRA-FORTE, A really small SMR for the Canadian market."
Trans. Am. Nucl. Soc., 109 (2013) 2258-2260.
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Wallenius, J. and Hussein, M. (2018a)
"Uranium nitride fuels for application in CANDU reactors."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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Wallenius, J., Bortot, S. and Mickus, I. (2018b)
"Unprotected Transients in SEALER: a Small Lead-Cooled Reactor for Commercial Power Production in Arctic Regions."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Wallenius, J., Qvist, S., Mickus, I., Bortot, S., Szakalos, P. and Ejenstam, J. (2018c)
"Design of SEALER, a very small lead-cooled reactor for commercial power production in off-grid applications."
Nucl. Eng. Design, 338 (2018) 23-33
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Wallenius, J. (2019a)
"Maximum efficiency nuclear waste transmutation."
Ann. Nucl. Energy, 125 (2019) 74-79.
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Wallenius, J. and Bortot, S. (2019b)
"A new paradigm for breeding of nuclear fuel."
Ann. Nucl. Energy, 133 (2019) 816-819.
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Walters, W. (2017)
"Application of the RAPID Fission Matrix Methodology to 3-D Whole-core Reactor Transport."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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Walters, W. (2018a)
"A Method for Adaptive Stratified Sampling with Angular Source Biasing."
Trans. Am. Nucl. Soc., 119 (2018) 590-593.
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Walter, W., Roskoff, N. and Haghighat, A. (2018b)
"The RAPID Fission Matrix Approach to Reactor Core Criticality Calculations."
Nucl. Sci. Eng., 192 (2018) 21-39.
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Wang, L., Guo, J., Li, F., Hou, J. and Ivanov, K. (2016)
"Effect of Double Heterogeneity Treatment on Neutronics Modeling of HTGR Unit Cell."
In proc. HTR 2016, Las Vegas, NV, Nov. 6-10, 2016.
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Wang, Y., Schunert, S., Ortensi, J., Gleicher, F., Laboure, V., Baker, B., DeHart, M. and Martineau, R. (2017)
"Demonstration of MAMMOTH Strongly-Coupled Multiphysics Simulation with the Godiva Benchmark Problem."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Wang, Y., Ortensi, J., Schunert, S. and Laboure, V. (2018)
"A Pebble Tracking Transport Algorithm for Pebble Bed Reactor Analysis."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Ward, A., Hall, A. and Downar, T. (2014)
"A Preliminary Analysis of the Accuracy of Homogenized 2D Cross Sections in 3D Nodal Calculations for BWRs."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Wendt, B. and Kerby, L. (2017)
"MultiApp Transfers in the MOOSE Framework Based on Functional Expansions."
Trans. Am. Nucl. Soc., 117 (2017) 735-738.
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Wendt, B. and Kerby, L. (2018)
"Monte Carlo Tally Convergence: Runtime Comparisons Between Functional Expansion Tallies and Mesh Tallies."
Trans. Am. Nucl. Soc., 118 (2018) 404-407.
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| • |
Wendt, B., Kerby, L., Tumulak, A. and Leppänen, J. (2018)
"Advancement of functional expansion capabilities: Implementation and optimization in Serpent 2."
Nucl. Eng. Design, 334 (2018) 138-153.
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| • |
Wicaksono, D., Grimm, P., Vasiliev, A., Hursin, M., Perret, G. and Ferroukhi, H. (2014)
"Validation of Two Monte Carlo Codes for LWR Burnup Calculations."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Wolniewicz, P., Hellesen, C., Håkansson, A., Jacobsson Svärd, S. J., Jansson, P. and Österlund, M. (2013a)
"Detecting neutron spectrum perturbations due to coolant density changes in a small lead-cooled fast nuclear reactor."
Ann. Nucl. Energy, 58 (2013) 102-109.
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| • |
Wolniewicz, P., Håkansson, A., Jansson, P, Jacobsson Svärd, S. (2013b)
"Feasibility study of detection of coolant void in liquid metal cooled fast reactors using changes in the neutron spectrum."
Nucl. Eng. Design, 265 (2013) 1255-1265.
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Wolniewicz, P., Håkansson and Jansson, P. (2015)
"Detection of coolant void in lead-cooled fast reactors."
Ann. Nucl. Energy, 85 (2015) 1096-1103.
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| • |
Woolstenhulme, N., Bess, J., Davis, C., Dusanter, L., Folsom, C., Parry, J., Shorthill, T. and Zhao, H. (2018)
"Optimization Options for Narrowing Transient Testing Pulse Widths Necessary to Enhance LWR RIA Simulations in the TREAT Facility."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Wooten, D. and Fratoni, M. (2016)
"Enhanced Fidelity Depletion for Molten Salt Reactors."
In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
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| • |
Wu, X. and Kozlowski, T. (2014)
"Uncertainty quantification for coupled Monte Carlo and thermal-hydraulics codes."
Trans. Am. Nucl. Soc., 110 (2014) 189-191.
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| • |
Wu, X. and Kozlowski, T. (2014)
"Development of a New Convergence Criterion for Monte Carlo Simulation with Thermal-Hydraulics Feedback."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Wu, X. and Kozlowski, T. (2015a)
"Coupling of system thermal–hydraulics and Monte-Carlo code: Convergence criteria and quantification of correlation between statistical uncertainty and coupled error."
Ann. Nucl. Energy, 75 (2015) 377-387.
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| • |
Wu, X., Kozlowski, T. and Hales, J. (2015b)
"Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions."
Ann. Nucl. Energy, 85 (2015) 763-775.
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| • |
Wyant, T. and Petrovic, B. (2012b)
"Numerical study of error propagation in Monte Carlo depletion simulations."
In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
|
| • |
Wyant, T. and Petrovic, B. (2013)
"Uncertainty propagation in full-core Monte Carlo depletion simulations using Serpent."
In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
|
| • |
Xing, Z. and Shwageraus, E. (2017)
"Coupling FHR Core Design with Power Conversion System."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
|
| • |
Xing, Z. and Shwageraus, E. (2018)
"Molten Salt Coolant Reactivity Feedback in Alternative FHR Designs."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Yahya, M., Kim, Y. and Chung, C. (2014a)
"A Novel Burnable Absorber Concept for PWR: BigT (Burnable Absorber-Integrated Guide Thimble)."
Trans. Korean Nucl. Soc., Spring Meeting, Jeju, Korea, May 29-30, 2014.
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| • |
Yahya, M., Yu, H. and Kim, Y. (2014b)
"A Burnable Absorber-Integrated Control Rod Guide Thimble for PWR."
Trans. Am. Nucl. Soc., 110 (2014) 593-594.
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| • |
Yahya, M., Yu, H. and Kim, Y. (2014c)
"BigT: a New Burnable Absorber Concept for PWR."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Yahya, M. and Kim, Y. (2014d)
"Application of the BigT Burnable Absorber to AP1000 Core for a Soluble Boron Free Operation."
Trans. Am. Nucl. Soc., 111 (2014) 1208-1210.
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| • |
Yahya, M. and Kim, Y. (2015a)
"Application of the BigT Burnable Absorber to AP1000 First Core."
Trans. Am. Nucl. Soc., 112 (2015) 811-813.
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| • |
Yahya, M., Hartanto D. and Kim, Y. (2015b)
"A Neutronics Study on Annular Fuel Filled with Burnable Absorber."
Trans. Am. Nucl. Soc., 113 (2015) 1262-1264.
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| • |
Yahya, M., Yu, H. and Kim, Y. (2016a)
"Burnable absorber-integrated Guide Thimble (BigT) – I: design concepts and neutronic characterization on the fuel assembly benchmarks."
J. Nucl. Sci. Technol., 53 (2016) 1048-1060. |
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Yahya, M., and Kim, Y. (2016b)
"Burnable absorber-integrated guide thimble (BigT) – II: application to 3D PWR core design."
J. Nucl. Sci. Technol., 53 (2016) 1521-1527. |
| • |
Yahya, M. Kim, Y. and Chung, C. (2016c)
"Criticality Control of a High-Performance Soluble-Boron-Free Small Modular Reactor Core."
Trans. Am. Nucl. Soc., 115 (2016) 1184-1185.
|
| • |
Yahya, M. and Kim, Y. (2017)
"Monte Carlo-Deterministic Hybrid Analysis for a Soluble-Boron-Free SMR."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Younan, S. and Novog, D. (2018)
"Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors."
Sci. Technol. Nucl. Install., 2018 (2018), Article ID 5327146.
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| • |
Younker, I. and Fratoni, M. (2016)
"Neutronic evaluation of coating and cladding materials for accident tolerant fuels."
Prog. Nucl. Energy, 88 (2016) 10-18.
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Yu, H., Kim, Y. and Kim, H. (2014a)
"Application of the BigT Burnable Absorber to an OPR1000 Core."
Trans. Korean Nucl. Soc., Spring Meeting, Jeju, Korea, May 29-30, 2014.
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| • |
Yu, H., Yahya, M. and Kim, Y. (2014b)
"Application of the BigT Burnable Absorber to a Soluble Boron-free PWR Core."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Yu, H., Hartanto, D., Moon, J. and Kim, Y. (2014c)
"A Conceptual Study of a Supercritical CO2 -Cooled Micro Modular Reactor."
In proc. HTR-2014, Weihai, China, Oct. 27-31, 2014.
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| • |
Zabriskie, A., Baker, B., Ortensi, J., DeHart, M. and Marcum, W. (2018)
"Self-Limiting Transient Pulse Simulation Method Exhibiting Time Lag Phenomenon Using Mammoth."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Zanetti, M., Luzzi, L., Cammi, A., Fiorina, C. (2014)
"An Innovative Approach to Dynamics Modeling and Simulation of the Molten Salt Reactor Experiment."
In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
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| • |
Zanetti, M., Cammi, A., Fiorina, C. and Luzzi, L. (2015)
"A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics."
Prog. Nucl. Energy, 83 (2015) 82-98.
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Zerovnik, G., Abrozi, K., Calic, D., Fiorito, L., Govers, K., Hernandes Solis, A., Kos, B., Kromar, M., Schillebeeck, P., and Stankovskiy, A. (2019)
"Characterization of Spent PWR Fuel for Decay Heat, Neutron and Gamma-Ray Emission: Code Comparison."
In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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| • |
Zhang, G., Fratoni, M., Vujic, J. and Greenspan, E. (2015)
"Once-Through Thorium Blanket Driven to Very High Burnup by Fast Reactor Excess Neutrons."
Trans. Am. Nucl. Soc., 112 (2015) 762-766.
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Zhang, G., Fratoni, M. and Greenspan, E. (2018)
"Improved resource utilization by advanced burner reactors with breed-and-burn blankets."
Prog. Nucl. Energy, 106 (2018) 440-454.
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| • |
Zhang, Y. and Wallenius, J. (2009)
"Upper Limits to Americium Concentration in Medium Size Sodium Cooled Fast Reactors."
In proc. Global 2009, Paris, France, Sept. 6-11, 2009.
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Zhang, Y., Wallenius, J. and Fokau, A. (2010)
"Transmutation of americium in a medium size sodium cooled fast reactor design."
Ann. Nucl. Energy, 37 (2010) 629-638.
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Zhang, Y., Wallenius, J. and Jolkkonen, M. (2013)
"Transmutation of americium in a large sized sodium-cooled fast reactor loaded with nitride fuel."
Ann. Nucl. Energy, 53 (2013) 26-34.
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Zhang, Y. and Wallenius, J. (2014)
"Upper limits to americium concentration in large sized sodium-cooled fast reactors loaded with metallic fuel."
Ann. Nucl. Energy, 70 (2014) 180–187.
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Zhang, Y. and Mikityuk, K. (2016)
"Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuels."
Ann. Nucl. Energy, 87 (2016) 761-771.
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Zhang, Q., Wang, X., Zhang, Y., Chi, X., Liang, L., Zhuang, K. and Wang, C. (2019)
"Neutronic analysis for potential Accident Tolerant Fuel UO2-BeO in the light water reactor."
Ann. Nucl. Energy, 127 (2019) 278-292.
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| • |
Zhou, H., Seker, V., Xu, Y. and Downar, T. (2017)
"Uncertainty Analysis of TREAT Standard Fuel Assembly and Minimum Critical Core Models."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Zhou, H., Seker, V. and Downar, T. (2018)
"Uncertainty Quantification of TREAT Transient Test 2857 with Spectral Projection Techniques."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Zhou, S., Yang, W., Park, T. and Wu, H (2018)
"Fuel cycle analysis of molten salt reactors based on coupled neutronics and thermal-hydraulics calculations (2018)."
Ann. Nucl. Energy, 114 (2018) 369-383.
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| • |
Zilly, M., Bousquet, J., Velkov, K., Ban, Y. and Joo, H. (2017)
"Analyzing the BEAVRS HZP case with KMACS using 2-group data from SCALE-NEWT, HELIOS and nTRACER."
In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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| • |
Zilly, M., Pletz, K., Bostelmann, F., Aures, A., Velkov, K. and Stoll, U. (2018)
"Fuel Assembly Bowing: Impact of Inter-assembly Gap on Power Distribution."
In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
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| • |
Zorla, E., Ipbuker, C., Biland, A., Kiisk, M., Kovaljovc, S., Tkaczyk, A. and Gulik, V. (2017)
"Radiation shielding properties of high performance concrete reinforced with basalt fibers infused with natural and enriched boron."
Nucl. Eng. Design, 313 (2017) 306-318.
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Zweibaum, N., Cao, G., Cisneros, A., Kelleher, B., Laufer, M., Scarlat, R., Seifried, J., Anderson, M. Forsberg, C., Greenspan, E., Hu, L., Peterson, P. and Sridharan, K. (2014)
"Phenomenology, methods and experimental program for fluoride-salt-cooled, high-temperature reactors (FHRs)."
Prog. Nucl. Energy, 77 (2014) 390-405.
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