Analysis of a multigroup stylized CANDU half-core benchmark |
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| Authors: | Justin M. Pounders Farzad Rahnema Dumitru Serghiuta |
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| Affiliation: | 1. Georgia Institute of Technology, George W. Woodruff School, Nuclear and Radiological Engineering/Medical Physics Programs, Atlanta, GA 30332-0405, United States;2. Canadian Nuclear Safety Commission, 280 Slater Street, Ottawa, Ontario, Canada K1P 5S9 |
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| Abstract: | 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. |
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| Keywords: | CANDU Benchmark problem Whole core neutron transport Monte Carlo benchmark results Multigroup macroscopic cross section library and analysis |
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