蒙特卡罗粒子输运计算网格计数方法研究
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摘要
在进行反应堆数值模拟时,通过网格计数方法可以精细地统计整个堆芯中多种物理量的空间分布情况。本文基于超级蒙特卡罗核计算仿真软件系统SuperMC发展了一种反应堆静态物理参数的网格计数方法。通过日本原子能研究所临界实验装置TCA例题进行了数值验证,计算结果与MCNP计算结果吻合较好,表明了本文方法的可行性与正确性。
Mesh tally method can accurately count the distribution of various physical quantities in reactor numerical simulation.The mesh tally of static parameters of rectangular coordinate system and cylindrical coordinate system was studied,which based on Super Monte Carlo Simulation Program for Nuclear and Radiation Process SuperMC.The TCA criticality facility of Japan Atomic Energy Research Institute was carried out for validation.The feasibility and the correctness of the method were demonstrated by the match of calculation results of SuperMC and MCNP.
Mesh tally method can accurately count the distribution of various physical quantities in reactor numerical simulation.The mesh tally of static parameters of rectangular coordinate system and cylindrical coordinate system was studied,which based on Super Monte Carlo Simulation Program for Nuclear and Radiation Process SuperMC.The TCA criticality facility of Japan Atomic Energy Research Institute was carried out for validation.The feasibility and the correctness of the method were demonstrated by the match of calculation results of SuperMC and MCNP.
引文
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[19]Pengcheng Long,Qin Zeng,Tao He,et al.Development of a Geometry-Coupled Visual Analysis System for MCNP[J].Progress in Nuclear Science and Technology,2011,2:280-283.
[20]龙鹏程,罗月童,邹俊等.基于可编程图形处理器的可视化技术在中子学分析中的应用研究[J].核电子学与探测技术,2010,30(8):1042-1045.
[2]李树,田东风,邓力.中子时间常数的Monte Carlo计算方法[J].北京:清华大学学报(自然科学版),2007:1057-1061.
[3]李伟.基于堆外计数的堆芯功率分布重构方法研究[D].哈尔滨:哈尔滨工程大学,2009:1-3.
[4]John S.Hendricks.Superimposed Mesh Plotting in MCNP[R].LA-UR-01-1033,2001:3-5.
[5]Jaakko Leppanen.Serpent-a continuous energy Monte Carlo Reactor Physics Burnup Calculation Code User's Manual.March 6,2013:131-133.
[6]T.M.Sutton,T.J.Donovan et al The MC21 Monte Carlo Transport Code CJ].M&C+SNA 2007:4.
[7]曾勤,李莹,卢磊等.蒙特卡罗粒子输运计算自动建模程序MCAM在ITER核分析建模中的应用[J].原子核物理评论,2006,23(2):138-141.
[8]Mafizur Rahman,T.Suzaki,et al.Validation study of the Monte Carlo code MVP for analysis of two-region TCA critical experiments with PWR-type MOX fuels[J].Progress in Nuclear Energy,48(2006)703-726.
[9]Y.Wu,FDS Team.CAD-based Interface Programs for Fusion Neutron Transport Simulation[J].Fusion Engineering and Design,2009,84(7-11):1987-1992.
[10]吴宜灿,李莹,卢磊等.蒙特卡罗粒子输运计算自动建模程序系统的研究与发展.核科学与工程,2006,26(1):20-27.
[11]王国忠,党同强,熊健等.MCAM4.8在ITER建筑大厅中子学建模中的应用[J].核科学与工程,2011,31(4):352-353.
[12]Y.Li,L Lu,A.Ding,et al.Benchmarking of MCAM4.0 with the ITER 3D Model[J].Fusion Engineering and Design,2007,82(15):2861-2866.
[13]Guozhong Wang,Jian Xiong,Pengcheng Long,et al.Progress and Applications of MCAM:Monte Carlo Automatic Modeling Program for Particle Transport Simulation[J].Progress in Nuclear Science and Technology,2011,2:821-825.
[14]Dezheng Xu,Zhaozhong He,et al.Production and Testing of HENDL-2.1/CG Coarse-group Cross-section Library Based on ENDF/B-Ⅶ.0[J].Fusion Engineering and Design,2010,85(10-12):2105-2110.
[15]吴宜灿,胡丽琴,龙鹏程等.先进核能系统设计分析软件与数据库研发进展[J].核科学与工程。2010,30(1):55-64.
[16]WU YC,Xie ZS,et al.A discrete ordinates nodal method for one dimensional neutron transport calculation in curvilinear geometry[J].Nuclear Science and Engineering,1999,133(3):350-357.
[17]罗月童,龙鹏程,薛晔等.面向中子学分析的集成可视化平台SVIP的发展研究[J].核科学与工程,2007,27(4):374-378.
[18]吴宜灿,刘萍,胡丽琴等.大型集成概率安全分析软件系统的研究与发展[J].核科学与工程,2007,27(3):69-75.
[19]Pengcheng Long,Qin Zeng,Tao He,et al.Development of a Geometry-Coupled Visual Analysis System for MCNP[J].Progress in Nuclear Science and Technology,2011,2:280-283.
[20]龙鹏程,罗月童,邹俊等.基于可编程图形处理器的可视化技术在中子学分析中的应用研究[J].核电子学与探测技术,2010,30(8):1042-1045.