原子能科学技术Issue(z2)：483-487,5.DOI:10.7538/yzk.2013.47.S1.0483
基于OECD／NEA堆芯功率分布基准的RMC验证
Verification of RMC With Reactor Benchmark of Core Power Distribution Based on OECD/NEA
摘要
Abstract
The critical calculation capacity of RMC (Reactor Monte Carlo Code) was verified based on the core power distribution verification benchmark released by OECD /NEA . The data of ENDF/B-Ⅵ library were used by RMC , and the whole-core eigenvalues were calculated and the 1/8 pin-by-pin fission rate was counted . Comparisons were made among the benchmark eigenvalues and those outputs by the RMC code and MCNP .The eigenvalue calculation results are in good agreement with the reference and the outputs of MCNP .The fission rate calculated by this work has an average relative deviation of 2.89% compared with the reference , and 0.5% with MCNP .The fission rate and absorption rate of different nuclides were calculated as well as the eigenvalues of four different cells .The results agree well with the reference data , which indicates that RMC has a good performance in core critical calculation capacity and the results provide a direct reference for the similar problem calculation .关键词
蒙特卡罗程序/验证/堆芯基准题/特征值/反应率Key words
Monte Carlo code/verification/core benchmark/eigenvalue/reaction rate分类
能源科技引用本文复制引用
高彬,马续波,陈义学,余慧..基于OECD／NEA堆芯功率分布基准的RMC验证[J].原子能科学技术,2013,(z2):483-487,5.基金项目
国家科技重大专项资助项目（2011ZX06004-024-002；2011ZX06004-024-003）；新世纪优秀人才支持计划资助项目 （）
