5 Alcouffe R E, Baker R S, Turner S A, et al. PARTISN: a time-dependent, parallel neutral particle transport code system[R]. Los Alamos National Laboratory, 2002
[2]
6 Hannebutte U, Brown P N. Ardra: scalable parallel code system to perform neutron and radiation transport calculations[R]. Lawrence Livermore National Laboratory, 1999
[3]
7 Clouse C J. Parallel deterministic neutron transport with AMR[A]. In: F.R. Graziani, Springer-Verlag. Computational Methods in Transport[M], 2006: 499-512
[4]
8 Greenman G M, Procassini R J, Clouse C J. A monte carlo method for calculating initiation probability[C]. Joint Intl. Topical Mtg. on Mathematics, Computation, and Supercomputing in Nucl. Appl., Monterrey, CA, April 15-19, 2007
[5]
9 Baker R S. Deterministic methods for time-dependent stochastic neutron transport[C]. International Conference on Mathematics, Computational Methods Reactor Physics (MC 2009), Saratoga Springs, New York, May 3-7, 2009
[6]
1 Hansen G E. Assembly of fissionable material in the presence of weak neutron source[J]. Nuclear Science and Engineering, 1960, 8: 709-719
[7]
2 Bell G I. On the stochastic theory of neutron transport[J]. Nuclear Science and Engineering, 1965, 21: 390-401
[8]
3 Bell G I, Lee C E. On the probability of initiating a persistent fission chain[R]. Los Alamos National Laboratory, 1976
LIU Jianjun, WANG Zhe, ZHANG Ben’ai. Research of stochastic neutron transport equation’s numerial and analytic solution[J]. Chinese Journal of Nuclear Science and Engineering, 2006, 26(2):118-121
