三维并行程序JSNT对HBR-2装置的屏蔽计算与分析
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摘要
屏蔽计算是反应堆设计的重要环节之一,其计算结果直接影响核系统的寿命以及周边环境的辐射安全。JSNT是由中物院高性能数值模拟软件中心自主研发的三维离散纵标(S_N)中子/光子输运程序,采用区域分解实现大规模并行,具有较高的计算精度和计算效率。本文利用JSNT对HBR-2装置进行屏蔽计算,分析了辐照监督管处和中子剂量测量仪处的中子通量密度分布以及6个核素的放射性比活度,并与实验测量值进行了比较,发现网格划分对计算结果有较大影响,随着网格的加密,计算结果趋于实验值;除在中子剂量测量仪处的~(237)Np(n,f)~(137)Cs和~(238)U(n,f)~( 137)Cs外,计算结果与测量值的相对偏差均小于20%,满足工程要求。
Shielding calculation is one of important parts of nuclear reactor design. Its calculation results directly affect the lifetime of nuclear power plant and radiation safety of surrounding environment. JSNT is a three-dimensional massively paralleled discrete ordinate neutron/photon transport code, which is developed by CAEP Software Center for High Performance Numerical Simulation. Region decomposition is used to realize large-scale parallel computation, so JSNT has high simulation accuracy and computational efficiency. Based on geometry modeling of BHR-2, JSNT was used to carry out the shielding calculation and analysis. Three-dimensional neutron flux density distribution and specific radioactivity were calculated at the location of surveillance capsule and neutron dosimeter. The smaller the mesh, the better the agreement between the calculated results and the experimental values. Except for the ~(237)Np(n,f)~(137)Cs and ~(238)U(n,f)~(137)Cs at the location of neutron dosimeter, the relative deviation of calculated numerical results and experimental values is less than 20%, which meets the engineering requirements.
Shielding calculation is one of important parts of nuclear reactor design. Its calculation results directly affect the lifetime of nuclear power plant and radiation safety of surrounding environment. JSNT is a three-dimensional massively paralleled discrete ordinate neutron/photon transport code, which is developed by CAEP Software Center for High Performance Numerical Simulation. Region decomposition is used to realize large-scale parallel computation, so JSNT has high simulation accuracy and computational efficiency. Based on geometry modeling of BHR-2, JSNT was used to carry out the shielding calculation and analysis. Three-dimensional neutron flux density distribution and specific radioactivity were calculated at the location of surveillance capsule and neutron dosimeter. The smaller the mesh, the better the agreement between the calculated results and the experimental values. Except for the ~(237)Np(n,f)~(137)Cs and ~(238)U(n,f)~(137)Cs at the location of neutron dosimeter, the relative deviation of calculated numerical results and experimental values is less than 20%, which meets the engineering requirements.
引文
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[9] 闫宇航. 反应堆压力容器快中子注量计算方法研究[D]. 上海:上海交通大学,2012.
[2] CHENG T P, WEI J X, SHEN H Y, et al. Development of parallel 3D discrete ordinate transport problem on JASMIN framework[C]//7th International Conference Modelling and Simulating in Nuclear Science and Engineering. [S. l.]: [s. n.], 2015.
[3] 程汤培,张广春,魏军侠,等. 三位中子输运分流再平衡加速及其并行算法[J]. 强激光与粒子束,2017,29(9):129-136. CHENG Tangpei, ZHANG Guangchun, WEI Junxia, et al. Parallel partial current rebalance algorithm for neutron transport simulation[J]. High Power Laser and Particle Beams, 2017, 29(9): 129-136(in Chinese).
[4] 张广春,程汤培,邓力,等. 基于JSNT程序的压水堆屏蔽计算[J]. 强激光与粒子束,2017,29(3):94-98. ZHANG Guangchun, CHENG Tangpei, DENG Li, et al. Shielding calculations of PWR using JSNT code[J]. High Power Laser and Particle Beams, 2017, 29(3): 94-98(in Chinese).
[5] REMEC I, KAM F K. H.B.Robinson-2 pressure vessel benchmark[R]. USA: Oak Ridge National Laboratory, 1997.
[6] 谢仲生,邓力. 中子输运理论数值计算方法[M]. 西安: 西北工业大学出版社,2005.
[7] 马彦,付元光,秦桂明,等. 面向领域的大规模可视化建模工具JLAMT的设计与实现[J]. 计算物理, 2016,33(5):606-612. MA Yan, FU Yuanguang, QIN Guiming, et al. Design and development of auto-modeling tool JLAMT for field application of large-scale models[J]. Chinese Journal of Computational Physics, 2016, 33(5): 606-612(in Chinese).
[8] WHITE J E. BUGLE-96: A revised multigroup cross section library for LWR applications based on ENDF/B-Ⅵ release 3[C]//American Nuclear Society Radiation Protection & Shielding Topical Meeting. [S. l.]: [s. n.], 1996.
[9] 闫宇航. 反应堆压力容器快中子注量计算方法研究[D]. 上海:上海交通大学,2012.