Difference between revisions of "Delta- and surface-tracking"
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This a brief description on the delta-tracking based transport routine used in Serpent. The method is also used by other Monte Carlo codes, most notably in the HOLE geometry package in MONK and MCBEND. | This a brief description on the delta-tracking based transport routine used in Serpent. The method is also used by other Monte Carlo codes, most notably in the HOLE geometry package in MONK and MCBEND. | ||
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The original delta-tracking algorithm was introduced by Woodcock in 1965,<ref>Woodcock, E. R., Murphy, T., Hemmings, P. J., and Longworth, T. C. ''"Techniques used in the GEM code for Monte Carlo neutronics calculations in reactors and other systems of complex geometry."'' ANL-7050, Argonne National Laboratory, 1965.</ref> and a mathematical verification was derived by Coleman in 1968.<ref>Coleman, W. A. ''"Mathematical verification of a certain Monte Carlo sampling technique and applications of the technique to radiation transport problems."'' Nucl. Sci. Eng., '''31''' (1968) 76–81.</ref> The method is well described in a text book by Lux and Koblinger,<ref>Lux, I. and Koblinger, L. ''"Monte Carlo Particle Transport Methods: Neutron and Photon Calculations."'' CRC Press, Inc. (1991).</ref> and the basic routine used in Serpent in an article in Annals of Nuclear Energy from 2010.<ref>Leppänen, J. ''"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.</ref> | The original delta-tracking algorithm was introduced by Woodcock in 1965,<ref>Woodcock, E. R., Murphy, T., Hemmings, P. J., and Longworth, T. C. ''"Techniques used in the GEM code for Monte Carlo neutronics calculations in reactors and other systems of complex geometry."'' ANL-7050, Argonne National Laboratory, 1965.</ref> and a mathematical verification was derived by Coleman in 1968.<ref>Coleman, W. A. ''"Mathematical verification of a certain Monte Carlo sampling technique and applications of the technique to radiation transport problems."'' Nucl. Sci. Eng., '''31''' (1968) 76–81.</ref> The method is well described in a text book by Lux and Koblinger,<ref>Lux, I. and Koblinger, L. ''"Monte Carlo Particle Transport Methods: Neutron and Photon Calculations."'' CRC Press, Inc. (1991).</ref> and the basic routine used in Serpent in an article in Annals of Nuclear Energy from 2010.<ref>Leppänen, J. ''"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.</ref> | ||
Revision as of 15:15, 19 November 2015
This a brief description on the delta-tracking based transport routine used in Serpent. The method is also used by other Monte Carlo codes, most notably in the HOLE geometry package in MONK and MCBEND. The original delta-tracking algorithm was introduced by Woodcock in 1965,[1] and a mathematical verification was derived by Coleman in 1968.[2] The method is well described in a text book by Lux and Koblinger,[3] and the basic routine used in Serpent in an article in Annals of Nuclear Energy from 2010.[4]
The input parameters related to delta-tracking are:
- set dt - sets the probability threshold used for selecting between surface- and delta-tracking
- set forcedt - enforces the use of delta-tracking in a given list of materials
- set blockdt - enforces the use of surface-tracking in a given list of materials
- set minxs - definse the mean-free-path of collisions used to score the collision flux estimator
The output parameters are:
- TODO
Contents
Transport algorithm in Monte Carlo simulation
Surface- and delta-tracking
Hybrid method used in Serpent
Advantages and limitations
References
- ^ Woodcock, E. R., Murphy, T., Hemmings, P. J., and Longworth, T. C. "Techniques used in the GEM code for Monte Carlo neutronics calculations in reactors and other systems of complex geometry." ANL-7050, Argonne National Laboratory, 1965.
- ^ Coleman, W. A. "Mathematical verification of a certain Monte Carlo sampling technique and applications of the technique to radiation transport problems." Nucl. Sci. Eng., 31 (1968) 76–81.
- ^ Lux, I. and Koblinger, L. "Monte Carlo Particle Transport Methods: Neutron and Photon Calculations." CRC Press, Inc. (1991).
- ^ Leppänen, J. "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.
