基于OECD/NEA堆芯功率分布基准的RMC验证

高彬; 马续波; 陈义学; 余慧

doi:10.7538/yzk.2013.47.S1.0483

基于OECD/NEA堆芯功率分布基准的RMC验证

1.
华北电力大学核科学与工程学院,北京102206
2.
国家核电技术有限公司北京软件技术中心,北京100029

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- 刊出日期: 2013-12-19

Verification of RMC With Reactor Benchmark of Core Power Distribution Based on OECD/NEA

1.
School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China
2.
State Nuclear Power Software Development Center, Beijing 100029, China

摘要

摘要: 本文基于OECD/NEA的堆芯功率分布基准题对反应堆蒙特卡罗程序RMC临界计算功能进行了验证，并对RMC堆芯临界计算准确性进行了对比验证。本文中RMC采用ENDF/B-Ⅵ库计算了堆芯的特征值和统计了1/8堆芯的pin-by-pin裂变率，其结果与MCNP计算结果和参考解进行了对比。其中特征值计算结果与参考解吻合良好，裂变率与参考解的平均相对偏差为2.89%，与MCNP平均相对偏差仅为0.5%。另外，RMC计算了堆芯的4种不同栅元的特征值和栅元中不同核素的反应率，结果显示以上参数与参考解均吻合良好，说明RMC具有良好的临界计算功能，计算结果为求解类似问题时计算程序及条件选择提供直接参考。
- 蒙特卡罗程序 ,
- 验证 ,
- 堆芯基准题 ,
- 特征值 ,
- 反应率
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.
- Monte Carlo code ,
- verification ,
- core benchmark ,
- eigenvalue ,
- reaction rate

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参考文献(11)

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基于OECD/NEA堆芯功率分布基准的RMC验证

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出版历程

Verification of RMC With Reactor Benchmark of Core Power Distribution Based on OECD/NEA

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出版历程

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