Difference between revisions of "Delta- and surface-tracking"
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The input parameters related to delta-tracking are: | The input parameters related to delta-tracking are: | ||
| − | * [[input syntax manual#set dt|set dt]] | + | * [[input syntax manual#set dt|set dt]] - sets the probability threshold used for selecting between surface- and delta-tracking |
| + | * [[input syntax manual#set forcedt|set forcedt]] - enforces the use of delta-tracking in a given list of materials | ||
| + | * [[input syntax manual#set blockdt|set blockdt]] - enforces the use of surface-tracking in a given list of materials | ||
| + | * [[input syntax manual#set minxs|set minxs]] - definse the mean-free-path of collisions used to score the collision flux estimator | ||
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== Transport algorithm in Monte Carlo simulation == | == Transport algorithm in Monte Carlo simulation == | ||
Revision as of 15:11, 19 November 2015
This a brief description on the delta-tracking based transport routine used in Serpent. 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
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.
