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Monte Carlo method is used to simulate the radiation transport problems which have characteristics of high temperature, high pressure, multi-media and large deformation of the grid. Due to the nonuniform particle distribution and great difference in the sizes of the grid, it makes the statistical errors of the grid fluxes fluctuate wildly. The error accumulation after many time steps may even influence the truth of the calculated results. So the global source biasing technique is developed. The importance function used here for source biasing sampling is based on the grid fluxes and errors of the previous time step. This is much faster than the traditional methods for solving the adjoint equation. The numerical tests showed that the neutron flux errors in the important grids are obviously reduced by using global source biasing which adaptively assigns the number of particles in each grid.
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Keywords:
- time-dependent /
- radiation transport /
- Monte Carlo /
- source biasing sampling
[1] Du S H, Zhang S F, Feng T G, Wang Y Z, Xing J R 1989 Computer Simulation of Transport Problems (in Chinese) (Changsha: Hunan Science and Technology Press) p589 [杜书华、 张树发、 冯庭桂、 王元璋 1989 输运问题的计算机模拟(长沙:湖南科技出版社)第589页]
[2] LiuL Y, Gardner R P 1997 Nuclear Science and Engineering 125 188
[3] [4] [5] Zhang J T, He B, He X T, Chang T Q, Xu J B, Andereev N E 2001 Acta Phys. Sin. 50 921(in Chinese)[张家泰、 何 斌、 贺贤土、 常铁强、 徐林宝、 安德列夫 N. E. 2001 物理学报 50 921]
[6] [7] Lan K, He X T, Lai D X, Li S G 2006 Acta Phys. Sin. 55 3789 (in Chinese)[蓝 可、 贺贤土、 赖东显、 李双贵 2006 物理学报 55 3789]
[8] [9] Yuan G W, Hang X D, Sheng Z Q, Yue J Y 2009 Chin. J. Comput. Phys. 26 475 (in Chinese) [袁光伟、 杭旭登、 盛志强、 岳晶岩 2009 计算物理 26 475]
[10] Li S G, Hang X D, Li J H 2009 Chin. J. Comput. Phys. 26 247 (in Chinese)[李双贵、 杭旭登、 李敬宏 2009 计算物理 26 247]
[11] [12] [13] Yuan G W, Hang X D 2003 China Academy of Engineering Physics Annual Report 1 418(in Chinese)[袁光伟、 杭旭登 2003 工程物理研究院科技年报 1 418]
[14] Deng L, Yuan G X, Huang Z F, Xu H Y, Wang R H, Li S 2003 J. Numer. Meth. Comput. Appli. 24 111 (in Chinese) [邓 力、 袁国兴、 黄正丰、 许海燕、 王瑞宏、 李 树 2003 数值计算与计算机应用 24 111]
[15] [16] [17] Deng L, Zhang W Y, Huang Z F 2005 Chin. J. Comput. Phys. 22 527
[18] [19] Bell G I, Glasstone S (Translated by Qian L) 1979 Nuclear Reactor Theory (Beijing: Atomic Energy Press) p16 [贝尔G I, 格拉斯登S著 千里译 1979 核反应堆理论 (北京: 原子能出版社) 16]
[20] Xie Z S, Deng L 2005 Numerical Methods of Neutron Transport Theory (Xian: Northwestern Polytechnical University Press) p380 (in Chinese) [谢仲生、 邓 力 2005 中子输运理论数值方法 (西安: 西北工业大学出版社) 第380页]
[21] [22] [23] Emmett M B 1985 A Monte Carlo Radiation Transport Code with Array Geometry Capability MORSE-CGA ORNL-6174
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[1] Du S H, Zhang S F, Feng T G, Wang Y Z, Xing J R 1989 Computer Simulation of Transport Problems (in Chinese) (Changsha: Hunan Science and Technology Press) p589 [杜书华、 张树发、 冯庭桂、 王元璋 1989 输运问题的计算机模拟(长沙:湖南科技出版社)第589页]
[2] LiuL Y, Gardner R P 1997 Nuclear Science and Engineering 125 188
[3] [4] [5] Zhang J T, He B, He X T, Chang T Q, Xu J B, Andereev N E 2001 Acta Phys. Sin. 50 921(in Chinese)[张家泰、 何 斌、 贺贤土、 常铁强、 徐林宝、 安德列夫 N. E. 2001 物理学报 50 921]
[6] [7] Lan K, He X T, Lai D X, Li S G 2006 Acta Phys. Sin. 55 3789 (in Chinese)[蓝 可、 贺贤土、 赖东显、 李双贵 2006 物理学报 55 3789]
[8] [9] Yuan G W, Hang X D, Sheng Z Q, Yue J Y 2009 Chin. J. Comput. Phys. 26 475 (in Chinese) [袁光伟、 杭旭登、 盛志强、 岳晶岩 2009 计算物理 26 475]
[10] Li S G, Hang X D, Li J H 2009 Chin. J. Comput. Phys. 26 247 (in Chinese)[李双贵、 杭旭登、 李敬宏 2009 计算物理 26 247]
[11] [12] [13] Yuan G W, Hang X D 2003 China Academy of Engineering Physics Annual Report 1 418(in Chinese)[袁光伟、 杭旭登 2003 工程物理研究院科技年报 1 418]
[14] Deng L, Yuan G X, Huang Z F, Xu H Y, Wang R H, Li S 2003 J. Numer. Meth. Comput. Appli. 24 111 (in Chinese) [邓 力、 袁国兴、 黄正丰、 许海燕、 王瑞宏、 李 树 2003 数值计算与计算机应用 24 111]
[15] [16] [17] Deng L, Zhang W Y, Huang Z F 2005 Chin. J. Comput. Phys. 22 527
[18] [19] Bell G I, Glasstone S (Translated by Qian L) 1979 Nuclear Reactor Theory (Beijing: Atomic Energy Press) p16 [贝尔G I, 格拉斯登S著 千里译 1979 核反应堆理论 (北京: 原子能出版社) 16]
[20] Xie Z S, Deng L 2005 Numerical Methods of Neutron Transport Theory (Xian: Northwestern Polytechnical University Press) p380 (in Chinese) [谢仲生、 邓 力 2005 中子输运理论数值方法 (西安: 西北工业大学出版社) 第380页]
[21] [22] [23] Emmett M B 1985 A Monte Carlo Radiation Transport Code with Array Geometry Capability MORSE-CGA ORNL-6174
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