Analysis of a multigroup stylized CANDU half-core benchmark

作者：Pounders Justin M; Rahnema Farzad^*; Serghiuta Dumitru

来源：Annals of Nuclear Energy, 2011, 38(9): 2024-2078.

DOI：10.1016/j.anucene.2011.03.011

• CANDU
• Benchmark problem
• Whole core neutron transport
• Monte Carlo benchmark results
• Multigroup macroscopic cross section library and analysis

An 8-group cross section library is provided to augment a previously published 2-group 3D stylized half-core Canadian deuterium uranium (CANDU) reactor benchmark problem. Reference eigenvalues and selected pin and bundle fission rates are also included. This benchmark is intended to provide computational reactor physicists and methods developers with a stylized model problem in more than two energy groups that is realistic with respect to the underlying physics. In addition to transport theory code verification, the 8-group energy structure provides reactor physicist with an ideal problem for examining cross section homogenization and collapsing effects in a full-core environment. To this end, additional 2-, 4- and 47-group full-core Monte Carlo benchmark solutions are compared to analyze homogenization-free transport approximations incurred as a result of energy group condensation.

• 出版日期2011-9