期刊文献+

三维离散纵标-蒙特卡罗耦合方法在核电厂堆腔漏束计算中的应用 被引量:2

3D Discrete Ordinates-Monte Carlo Coupling Method for Nuclear Power Plant Cavity Streaming Calculation
下载PDF
导出
摘要 三维离散纵标-蒙特卡罗(SN-MC)耦合方法结合了SN方法计算速度快和MC方法几何描述精确的优点,可以在较短的时间内完成堆腔辐射漏束辐射场计算.以秦山一期反应堆和CAP1400反应堆为研究对象,采用三维SNMC耦合方法进行了堆腔漏束的计算,并和测量值以及其它方法的计算结果进行比较,验证SN-MC耦合方法理论模型和程序的正确性,为后续提高堆腔漏束计算精度和效率提供基础. By combining advantages of SN method ( high calculational efficiency) and advantages of MC method ( fine geometrical modelling), three-dimensional discrete ordinates-Monte Carlo method (3D SN-MC coupling method) is able to calculate cavity streaming dose rate in short time. SN-MC coupling method is applied on Qinshan No. 1 reactor and CAP1400 reactor cavity streaming calculation. Results of SN-MC coupling method are compared with measurements and results of MCNP bootstrapping method. It shows that theoretical model and codes of 3D SN-MC coupling method are both correct.
出处 《计算物理》 CSCD 北大核心 2016年第5期599-605,共7页 Chinese Journal of Computational Physics
关键词 堆腔漏束 注量率 剂量率 离散纵标方法 蒙特卡罗方法 reactor cavity streaming fluence rate dose rate discrete ordinates method Monte Carlo method
  • 相关文献

参考文献2

二级参考文献8

  • 1Emmett M B,Burgart C E,Hoffman T J. DOMINO,a general purpose code for coupling discrete ordinates and Monte Carlo radiation transport calculations,ORNL-4853[R].USA:ORNL,1973. 被引量:1
  • 2Eggleston J E,Abdou M A,Youssef M Z. The use of MCNP for neutronics calculations within large buildings of fusion facilities[J].Fusion Engineering and Design,1998.281-288. 被引量:1
  • 3Masahiko Kurosawa. TORT/MCNP coupling method for the calculation of neutron flux around a core of BWR[J].Radiation Protection Dosimetry,2005,(1-4):513-517. 被引量:1
  • 4谢仲生.核反应堆物理数值计算[M]北京:原子能出版社,1997. 被引量:1
  • 5RhoadesW A,Simpson D B. The TORT Three-dimensional Discrete Ordinates Neuron /Photon Trans port Code ORNL/TM13221[R].Oak Ridge National Laboratory,1997. 被引量:1
  • 6BRIESMEISTER J F. MCNP:A general Monte Carlo N-particle transport code,version 4C,LA-13709-M[R].USA:LANL,2000. 被引量:1
  • 7WIENKE H,HERMAN M. FENDL/MG-2.0 and FENDL/MC-2.0,the processed cross-section libraries for neutronphoton transport calculations,version 1[R].Vienna,Austria:Nuclear Data Section,International Atomic Energy Agency,1998. 被引量:1
  • 8钟兆鹏,施工,胡永明.用MCNP程序计算水平辐照孔道屏蔽[J].清华大学学报(自然科学版),2001,41(12):16-18. 被引量:14

共引文献10

同被引文献37

引证文献2

二级引证文献6

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