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Preliminary study on CAD-based method of characteristics for neutron transport calculation 被引量：2

Preliminary study on CAD-based method of characteristics for neutron transport calculation
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摘要 Our new method makes use of a CAD-based automatic modeling tool, MCAM, for geometry modeling and ray tracing of particle transport in method of characteristics （MOC）. It was found that it could considerably enhance the capability of MOC to deal with more complicated models for neutron transport calculation. In our study, the diamond-difference scheme was applied to MOC to reduce the spatial discretization errors of the fiat flux approximation. Based on MCAM and MOC, a new 2D MOC code was developed and integrated into the SuperMC system, which is a Super Multi-function Computational system for neutronics and radiation simulation. The numerical results demonstrated the feasibility and effectiveness of the new method for neutron transport calculation in MOC. Our new method makes use of a CAD-based automatic modeling tool, MCAM, for geometry modeling and ray tracing of particle transport in method of characteristics （MOC）. It was found that it could considerably enhance the capability of MOC to deal with more complicated models for neutron transport calculation. In our study, the diamond-difference scheme was applied to MOC to reduce the spatial discretization errors of the fiat flux approximation. Based on MCAM and MOC, a new 2D MOC code was developed and integrated into the SuperMC system, which is a Super Multi-function Computational system for neutronics and radiation simulation. The numerical results demonstrated the feasibility and effectiveness of the new method for neutron transport calculation in MOC.
作者 陈珍平 郑华庆 孙光耀 宋婧 郝丽娟 胡丽琴 吴宜灿
机构地区 University of Science and Technology of China Institute of Nuclear Energy Safety Technology Chinese Academy of Sciences
出处 《Chinese Physics C》 SCIE CAS CSCD 2014年第5期114-120,共7页 中国物理C（英文版）
基金 Supported by National Special Program for ITER(2011GB113006) Strategic Priority Research Program of Chinese Academy of Sciences(XDA03040000) National Natural Science Foundation of China(91026004)
关键词 method of characteristics neutron transport calculation CAD geometry modeling method of characteristics, neutron transport calculation, CAD, geometry modeling
分类号 O571.5 [理学—粒子物理与原子核物理]
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参考文献29

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同被引文献18

  • 1吴宜灿,李莹,卢磊,丁爱平,胡海敏,曾勤,罗月童,郑善良,黄群英,陈义学.Research and development of the automatic modeling system for Monte Carlo particle transport simulation[J].核科学与工程,2006,26(1):20-27. 被引量：58
  • 2WU Y, FDS Team. Conceptual design activitiesof FDS series fusion power plants in China[J].Fusion Engineering and Design,2006,81 (23-24) : 2 713-2 718.
  • 3WU Yican, FDS Team. Conceptual design of theChina fusion power plant FDS- II [J]. Fusion En-gineering and Design,2008,83 (10-12) : 1 683-1689.
  • 4WU Y C, ZHU X X, ZHENG S L,et al. Neu-tronics analysis of dual-cooled waste transmuta-tion blanket for the FDS[J]. Fusion Engineeringand Design,2002,63-64: 133-138.
  • 5QIU L, WU Y, XIAO B,et al. A low aspect ra-tio Tokamak transmutation system [J]. NuclearFusion, 2000 , 40 : 629-633.
  • 6WU Y,ZHENG S, ZHU X,et al. Conceptualdesign of the fusion-driven subcritical systemFDS- I [J]. Fusion Engineering and Design B,2006,81: 1 305-1 311.
  • 7WU Y, XIE Z,FISCHER U. A discrete ordi-nates nodal method for one-dimensional neutrontransport calculation in curvilinear geometries[J]. Nuclear Science and Engineering? 1999,133(3): 350-357.
  • 8WU Y,FDS Team. CAD-based interface pro-grams for fusion neutron transport simulation[J]. Fusion Engineering and Design, 2009,84 :1987-1 992.
  • 9HU H, WU Y,CHEN M,et al. Benchmarkingof SNAM with the ITER 3D model [J]. FusionEngineering and Design, 2007,82: 2 867-2 871.
  • 10WU Yican, SONG Jing,ZHENG Huaqing, etal. CAD-based Monte Carlo program for inte-grated simulation of nuclear system SuperMC[J], Annals of Nuclear Energy, Doi: 10. 1016/j.anucene. 2014. 08. 058.

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二级引证文献6

Chinese Physics C
2014年 第5期

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