Validation and verification

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This page collects together all documents related to Serpent validation. The different categories are listed below. Each entry should include one or several references to publicly accessible documents where the results are reported. If you have additional documentation related to an already listed case, you can just add the reference in the list.

Serpent input and output files can be also be provided. When the input consists of multiple files, link to zip or gzip archives.

Criticality

This section lists calculation cases from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP)[1] and other sources. The main (but not only) purpose of the calculations is validation for criticality safety. The difference to experim

ICSBEP Criticality Benchmarks

ICSBEP ID Experiment Description Results Refs. Files Added by Date
HEU-MET-FAST-001 Godiva Bare sphere of highly enriched uranium keff, βeff [2] input JLe / VTT 2015/11/18
HEU-MET-FAST-002 Topsy Highly enriched uranium sphere surrounded by a thick reflector of natural uranium keff, βeff [2] N/A JLe / VTT 2015/11/18
PU-MET-FAST-001 Jezebel Bare sphere of plutonium keff, βeff [2] input JLe / VTT 2015/11/18
PU-MET-FAST-006 Popsy Plutonium sphere surrounded by a thick reflector of natural uranium keff, βeff [2] input JLe / VTT 2015/11/18
U233-MET-FAST-001 Skidoo Bare sphere of U-233 keff, βeff [2] input JLe / VTT 2015/11/18
U233-MET-FAST-006 Flattop23 U-233 sphere surrounded by a thick reflector of natural uranium keff, βeff [2] input JLe / VTT 2015/11/18
IEU-MET-FAST-007 BigTen Large all-uranium-metal cylindrical core surrounded by a thick reflector of natural uranium keff, αR [2] N/A JLe / VTT 2015/11/18
IEU-MET-FAST-010 ZPR-U9 Cylindrical assembly of uranium metal with a thick depleted uranium reflector keff, βeff [2] N/A JLe / VTT 2015/11/18
MIX-MET-FAST-011 ZPR-MOX Cylindrical assembly of mixed fissile plutonium and uranium metal reflected by graphite keff, βeff [2] N/A JLe / VTT 2015/11/18
HEU-MET-INTER-001 ZPR-HEU Highly enriched uranium/iron cylinder reflected by stainless steel keff, βeff [2] N/A JLe / VTT 2015/11/18
PU-MET-INTER-002 ZPR-Pu Cylindrical plutonium/carbon/stainless steel assembly with stainless steel and iron reflectors keff, βeff [2] N/A JLe / VTT 2015/11/18
LEU-SOL-THERM-004 Stacy-029, -033, -046 Water-reflected cylindrical tank with uranyl nitrate solution keff, αR [2] N/A JLe / VTT 2015/11/18
LEU-SOL-THERM-007 Stacy-030 Unreflected cylindrical tank with uranyl nitrate solution keff, αR [2] input JLe / VTT 2015/11/18
LEU-SOL-THERM-016 Stacy-125 Water-reflected slabs of enriched uranyl nitrate solution keff, αR [2] N/A JLe / VTT 2015/11/18
LEU-SOL-THERM-021 Stacy-215 Unreflected cylindrical tank of uranyl nitrate solution keff, αR [2] N/A JLe / VTT 2015/11/18

Other Criticality Experiments

Experiment Description Results Refs. Files Added by Date
SNEAK-7A Unmoderated PuO2/UO2 core with a depleted uranium reflector keff, βeff [2] N/A JLe / VTT 2015/11/18
SNEAK-7B Unmoderated PuO2/UO2 core with a depleted uranium reflector keff, βeff [2] N/A JLe / VTT 2015/11/18
SNEAK-9C1 Unmoderated core UO2 core with a depleted uranium reflector keff, βeff [2] N/A JLe / VTT 2015/11/18
SNEAK-9C2 Unmoderated PuO2/UO2 core with Na and reflected by depleted uranium keff, βeff [2] N/A JLe / VTT 2015/11/18
Masurca-R2 Unmoderated core with enriched uranium fuel surrounded by a UO2–Na mixture blanket and by steel shielding keff, βeff [2] N/A JLe / VTT 2015/11/18
Masurca-Z2 Unmoderated core with plutonium and depleted uranium fuel surrounded by a UO2–Na mixture blanket and by steel shielding keff, βeff [2] N/A JLe / VTT 2015/11/18
FCA-XIX-1 Highly enriched uranium core surrounded by UO2/Na and uranium metal blanket regions keff, βeff [2] N/A JLe / VTT 2015/11/18
FCA-XIX-2 Plutonium/uranium core surrounded by UO2/Na and uranium metal blanket regions keff, βeff [2] N/A JLe / VTT 2015/11/18
FCA-XIX-3 Plutonium core surrounded by UO2/Na and uranium metal blanket regions keff, βeff [2] N/A JLe / VTT 2015/11/18
TCA Light water moderated low-enriched UO2 core in the tank-type critical assembly keff, βeff [2] N/A JLe / VTT 2015/11/18
IPEN Low enriched UO2 fuel rods inside a light water filled tank keff, βeff [2] N/A JLe / VTT 2015/11/18
Winco Slab tank assembly consisted of two thin coaxial slab tanks uranyl nitrate solution keff, αR [2] N/A JLe / VTT 2015/11/18
Sheba-II Enriched uranyl fluoride Solution High-Energy Burst Assembly (SHEBA) keff, αR [2] N/A JLe / VTT 2015/11/18
SHE-8 A hexagonal core with graphite matrix tubes and low enriched uranium fuel dispersed in graphite rods keff, αR [2] N/A JLe / VTT 2015/11/18

Application Specific Validation

Application Description Results Refs. Files Added by Date
SNF wet storage (78 cases) Hexagonal fuel assemblies separated by borated steel and water. keff [3] N/A VVa / VTT 2015/09/08

Research reactors & other experiments

This section collects studies involving full-scale modelling of research reactors and other experimental facilities. The results may include criticality calculations, but also other reactor physics data (flux or power distributions, spectral indices, etc.). Experiments focused on criticality safety validation alone should be included in the section above.

Calculation case Description Refs. Files Added by Date
Full-core burnup calculations for the OPAL research reactor First six operating cycles simulated at INVAP with Serpent 2, and compared to experimental results [4] N/A JLe / VTT 2016/03/02
Triga Mark II benchmark experiments Serpent 2 and MCNP calculations for the Triga Mark II reactor at JSI, Slovenia [5] N/A JLe / VTT 2016/09/16
FREYA fast critical experiments Characterization of the critical VENUS-F cores (SCK.CEN, Belgium) with Serpent 2 in the framework of the FP7 EURATOM project FREYA [6] N/A EF / HZDR 2017/05/15
Prismatic HTGR critical assembly calculations Reactor physics calculations for the VHTRC (JAEA, Japan) critical assembly using Serpent 2 and SCALE/KENO-VI [7] N/A JLe / VTT 2017/05/16
Pebble-bed HTGR critical assembly calculations Criticality calculations for the ASTRA (Kurchatov Institute, Russia) critical assembly using Serpent 2 [8] N/A JLe / VTT 2017/05/16
VVER-1000 mock-up calculations Criticality and other reactor physics calculations calculations for the LR-0 reactor (Rez, Czech Republic) using Serpent 2 [9] N/A JLe / VTT 2017/05/16

Burnup calculations

This section includes validation calculations involving fuel burnup. The results may include material compositions, criticality power distributions, etc. Since experimental data is scarce, also code-to-code comparisons may be included.

Calculation case Description Experimental data Refs. Files Added by Date
LWR-PROTEUS Phase-II calculations Isotopic compositions calculated using Serpent 2, MCNPX and VESTA and compared to experimental data YES [10] N/A JLe / VTT 2017/05/16
2D infinite-lattice PWR assembly burnup calculations (Krško NPP) keff and pin-power distributions calculated using Serpent 1, DRAGON, FA2D and SCALE/NEWT NO [11] N/A JLe / VTT 2017/05/16
Full-core GFR burnup calculations (Allegro) keff, flux spectra and isotopic compositions calculated using Serpent 2 and MONTEBURNS NO [12] N/A JLe / VTT 2017/05/16
Full-core SFR burnup calculations keff , power distribution and isotopic compositions calculated using Serpent 2 and KANEXT NO [13] N/A JLe / VTT 2017/05/16
OECD/NEA Burn-up Credit Criticality Safety Benchmark Phase VII calculations keff and isotopic compositions calculated using Serpent 2 and MCNP6 NO [14] N/A JLe / VTT 2017/05/16
CB6 benchmark on VVER-440 final disposal Decay and criticality calculations, comparison between Serpent 2 and ORIGEN NO [15] N/A JLe / VTT 2017/05/16
AER VVER-440 GD Fuel Burnup Benchmark keff and isotopic compositions calculated using Serpent 2 and compared to benchmark reference results NO [16] N/A JLe / VTT 2017/05/16
OECD/NEA benchmark for VVER-1000 fuel assembly with GD keff and isotopic compositions calculated using Serpent 2 and compared to benchmark reference results NO [16] N/A JLe / VTT 2017/05/16
OECD/NEA benchmark for VVER-1000 fuel assembly with LEU and MOX fuel keff, reactivity coefficients and isotopic compositions calculated using Serpent 2 and SCALE, and compared to benchmark reference results NO [17] N/A JLe / VTT 2017/05/16

Reduced-order methods

This section is intended for validation studies in which Serpent-generated cross sections are used for nodal diffusion and other reduced-order calculations. The studies may include comparison to experimental data or reference Serpent 3D calculations. Also comparison of group constants calculated by Serpent vs. results by other codes can be included.

Full-core calculations

Calculation case Code sequence Description Results Refs. Files Added by Date
MIT BEAVRS Benchmark Serpent-ARES 1000 MW PWR HZP initial core calculations using nodal diffusion code ARES Power distributions [18] N/A JLe / VTT 2015/11/18
MIT BEAVRS Benchmark Serpent-ARES 1000 MW PWR HFP initial core and burnup calculations using nodal diffusion code ARES Power distributions, control rod bank worths, boron dilution curve [19] input JLe / VTT 2016/08/26

Assembly-level code-to-code comparisons

Calculation case Reference codes Description Refs. Files Added by Date
Standard test cases run for each update MCNP5 PWR, BWR, CANDU, SFR and HTGR calculations using different cross section libraries [20] N/A JLe / VTT 2015/11/18

References

  1. ^ https://www.oecd-nea.org/science/wpncs/icsbep/handbook.html
  2. ^ Leppänen, J., Aufiero, M., Fridman, E., Rachamin, R., and van der Marck, S. "Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code." Ann. Nucl. Energy, 65 (2014) 272-279.
  3. ^ Valtavirta, V. "Criticality safety validation of Serpent for nuclear fuel wet storage calculations" Customer Report, VTT-CR-02424-17 (2017).
  4. ^ Ferraro, D. and Villarion, E. "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.
  5. ^ Ćalić, D., Žerovnik, G. Trkov, A. and Snoj, L. "Validation of the Serpent 2 code on TRIGA Mark II benchmark experiments." Appl. Radiat. Isot., 107 (2016) 165-170.
  6. ^ Fridman, E., Kochetkov, A., and Krása, A. "Modeling of FREYA fast critical experiments with the Serpent Monte Carlo code." Ann. Nucl. Energy, 108 (2017) 239–252.
  7. ^ Bostelmann, F., Hammer H., Ortensi, J., Strydom G., Velkov, K. and Zwermann, W.. "Criticality calculations of the Very High Temperature Reactor Critical Assembly benchmark with Serpent and SCALE/KENO-VI." Ann. Nucl. Energy, 90 (2016) 343–352.
  8. ^ Rintala, V., Suikkanen, H., Leppänen, J. and Kyrki-Rajamäki, R. "Modeling of realistic pebble bed reactor geometries using the Serpent Monte Carlo code." Ann. Nucl. Energy, 77 (2015) 223-230.
  9. ^ Chersola, D., Mazzini, G., Kostal, M., Miglierini, B., Hrehor, M., Lomonaco, G., Borreani, W. and Ruscak, M. "Application of Serpent 2 and MCNP6 to study different criticality configurations of a VVER-1000 mock-up." Ann. Nucl. Energy, 94 (2016) 109-122.
  10. ^ Pecchia, M., Wicaksono, D., Grimm, P., Vasilieva, A., Perret, G., Ferroukhi, H and Pautza, A. "Validation of Monte Carlo based burnup codes against LWR-PROTEUS Phase-II experimental data." Ann. Nucl. Energy, 97 (2016) 153-164.
  11. ^ Grgić, D., Jecmenica, R. and Pevec, D. "Lattice codes pin power prediction comparison." Nucl. Eng. Design, 246 (2012) 27-40.
  12. ^ Chersola, D., Lomonaco, G., Marotta, R. and Mazzini, G. "Comparison between SERPENT and MONTEBURNS codes applied to burnup calculations of a GFR-like configuration." Nucl. Eng. Design, 273 (2014) 542-554.
  13. ^ Lopez-Solis, R., François, J., Bastida-Ortiz, G., Becker, M. and Sánchez-Espinoza, V. "Fuel depletion analysis of a small sodium fast reactor with KANEXT and SERPENT." Ann. Nucl. Energy, 98 (2016) 26-35.
  14. ^ Herrero, J., Vasiliev, A., Pecchia, M., Ferroukhi, H. and Caruso, S. "Review calculations for the OECD/NEA Burn-up Credit Criticality Safety Benchmark." Ann. Nucl. Energy, 87 (2016) 48-57.
  15. ^ Lahtinen, T. "Solution of the CB6 benchmark on VVER-440 final disposal using the Serpent reactor physics code." Kerntechnik, 79 (2014) 303-313
  16. ^ Lötsch, T. "Fuel assembly burnup calculations for VVER fuel assemblies with the MONTE CARLO code SERPENT." Kerntechnik, 79 (2014) 295-302.
  17. ^ Mercatali, L., Venturini, A., Daeubler, M. and Sanchez, V. "SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark." Ann. Nucl. Energy, 83 (2015) 328-341.
  18. ^ Leppänen, J., Mattila, R. and Pusa, M. "Validation of the Serpent-ARES code sequence using the MIT BEAVRS benchmark - Initial core at HZP conditions." Ann. Nucl. Energy, 69 (2014) 212-225.
  19. ^ Leppänen, J. and Mattila, R. "Validation of the Serpent-ARES code sequence using the MIT BEAVRS benchmark – HFP conditions and fuel cycle 1 simulation." Ann. Nucl. Energy, 96 (2016) 324-331.
  20. ^ Standard validation cases at Serpent website