期刊文献+

堆用蒙特卡罗程序几何重复结构功能开发 被引量:8

Development of repeat geometry function in reactor Monte Carlo code RMC
下载PDF
导出
摘要 介绍了反应堆物理蒙特卡罗程序几何重复结构功能;以MCNP和反应堆用蒙特卡罗模拟程序RMC为例介绍了常见的重复结构输入及实现方式;简要介绍了三种用于几何层级、重复结构计算的加速功能;以大亚湾反应堆组件和全堆芯为例,比较了RMC和MCNP的计算时间,结果显示RMC相对于MCNP获得了3~9倍的加速效果。 This paper describes repeat geometry structure function and its application to reactor analysis Monte Carlo codes. Common repeat structure output and implementation is introduced using MCNP and RMC (RMC is a reactor Monte Carlo code developed by REAL team in Department of Engineering Physics, Tsinghua University) as exampies, and three speed-up methods for layer geometry structure and repeat geometry structure in RMC are presented. Examples of the Daya Bay reactor are calculated for comparison between MCNP and RMC, and results show that RMC speeds up by 3-9 times, compared with MCNP.
出处 《强激光与粒子束》 EI CAS CSCD 北大核心 2013年第1期219-222,共4页 High Power Laser and Particle Beams
基金 国家自然科学基金项目(91126017 11105080)
关键词 RMC 复杂几何 重复结构 蒙特卡罗 RMC complex geometry repeat structure Monte Carlo
  • 相关文献

参考文献5

  • 1X-5 Monte Carlo Team. MCNP--A general Monte Carlo N-Particle transport code, version 5. Volume II[R]. Los Alamos: Los Alamos Na- tional Laboratory, 2003.
  • 2孙嘉龙.RMC重复结构功能开发[D].北京:清华大学,2011.
  • 3孙嘉龙,余顶,余纲林,等.RMC复杂几何功能设计[R]//核反应堆系统设计技术重点实验室年报.2011:63-68.
  • 4李泽光,王侃,佘顶,徐琪,刘宇轩.自主堆用蒙卡模拟程序RMC2.0开发(英文)[J].核动力工程,2010,31(S2):43-47. 被引量:7
  • 5She Ding, Li Zeguang, Xu Qi, et al. Probability-neighbor method of accelerating geometry treatment in reactor Monte Carlo code RMC [C]//International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. 2011.

二级参考文献8

  • 1Forrest Brown.Fundamentals of Monte Carlo ParticleTransport. LA-UR-05-4983 . 2005
  • 2Jaakko Leppnen.Development of a New MonteCarloReactor Physics Code[]..2007
  • 3LIU Yuxuan,XU Qi,YU Ganglin,WANG Kan.AMethod of Optimized Utilization fo Point-wise DataFormat in Monte Carlo Code[].ICON.2010
  • 4Jaakko Leppnen.Two Practical Methods for UnionizedEnergy Grid Construction in Continuous-energy MonteCarlo Neutron Transport Calculation[].Annals ofNuclear Energy.2009
  • 5Nuclear Energy Agency/Working Party on Physics of Plutonium Recycling,Organisation for Economic Co-operation and Develop- ment.Fast Plutonium-Burner Reactors: Beginning of Life (A report by the Working Party on the Physics of Plutonium Recycling of the NEA Nuclear Science Committee: Physics of Plutonium Recycling, Volume 4)[]..1995
  • 6Brown F B,Nagaya Y.The MCNP5 random number gener-ator[].Transactions of the American Nuclear Society.2002
  • 7S.C. Frankle.A suite of criticality benchmarks for validating nuclear data[].LA- Los Alamos National Laboratory.1999
  • 8X-5 Monte Carlo Team.MCNP-A General Monte Carlo N-ParticleTransport Code. LA-CP-03-0245 . 2003

共引文献6

同被引文献68

引证文献8

二级引证文献14

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部