Calculating infinite-medium α-eigenvalue spectra with Monte Carlo using a transition rate matrix method

被引:9
作者
Betzler, Benjamin R. [1 ]
Kiedrowski, Brian C. [1 ]
Brown, Forrest B. [2 ]
Martin, William R. [1 ]
机构
[1] Univ Michigan, Dept Nucl Engn & Radiol Sci, Ann Arbor, MI 48109 USA
[2] Los Alamos Natl Lab, Los Alamos, NM 87545 USA
关键词
NUCLEAR-DATA; TECHNOLOGY; SCIENCE;
D O I
10.1016/j.nucengdes.2015.07.052
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The time-dependent behavior of the energy spectrum in neutron transport was investigated with a formulation, based on continuous-time Markov processes, for computing alpha eigenvalues and eigenvectors in an infinite medium. For this, a research Monte Carlo code called "TORTE" (To Obtain Real Time Eigenvalues) was created and used to estimate elements of a transition rate matrix. TORTE is capable of using both multigroup and continuous-energy nuclear data, and verification was performed. Eigenvalue spectra for infinite homogeneous mixtures were obtained, and an eigenfunction expansion was used to investigate transient behavior of the neutron energy spectrum. Published by Elsevier B.V.
引用
收藏
页码:639 / 644
页数:6
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