A 3D stylized half-core CANDU benchmark problem

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

来源：Annals of Nuclear Energy, 2011, 38(4): 876-896.

DOI：10.1016/j.anucene.2010.10.018

• CANDU
• Benchmark problem
• Benchmark results
• Whole core neutron transport
• Monte Carlo results
• Macroscopic cross section library

A 3D stylized half-core Canadian deuterium uranium (CANDU) reactor benchmark problem is presented. The benchmark problem is comprised of a heterogeneous lattice of 37-element natural uranium fuel bundles, heavy water moderated, heavy water cooled, with adjuster rods included as reactivity control devices. Furthermore, a 2-group macroscopic cross section library has been developed for the problem to increase the utility of this benchmark for full-core deterministic transport methods development. Monte Carlo results are presented for the benchmark problem in cooled, checkerboard void, and full coolant void configurations.

• 出版日期2011-4