期刊文献+

基于S/U分析方法的钍基熔盐装置核数据需求初步分析

Nuclear Data Requirement Analysis of TMSR Facility Basing on S/U Analysis
原文传递
导出
摘要 采用蒙特卡罗微扰方法计算钍基熔盐堆装置(MSRE)的keff对关键核数据的灵敏度,结合数据中心制作的多群协方差核数据库,应用S/U分析方法分析核数据引入的不确定度,给出了核素数据重要性的排序。 The sensitivity of keff of MSRE facility to the critical nuclear data is calculated by Monte Carlo perturbation method. Based on the multi-group covariance data library developed by China Nuclear Data Center, the uncertainty of nuclear data introduction is analyzed by S/U method, and the importance of the nuclear data is listed in order.
出处 《核动力工程》 EI CAS CSCD 北大核心 2014年第S2期80-82,共3页 Nuclear Power Engineering
关键词 钍基熔盐堆 核数据 灵敏度 不确定度 MSRE,Nuclear Data,Sensitivity,Uncertainty
  • 相关文献

参考文献4

  • 1M.B. Chadwick,M. Herman,P. Oblo?insky,M.E. Dunn,Y. Danon,A.C. Kahler,D.L. Smith,B. Pritychenko,G. Arbanas,R. Arcilla,R. Brewer,D.A. Brown,R. Capote,A.D. Carlson,Y.S. Cho,H. Derrien,K. Guber,G.M. Hale,S. Hoblit,S. Holloway,T.D. Johnson,T. Kawano,B.C. Kiedrowski,H. Kim,S. Kunieda,N.M. Larson,L. Leal,J.P. Lestone,R.C. Little,E.A. McCutchan,R.E. MacFarlane,M. MacInnes,C.M. Mattoon,R.D. McKnight,S.F. Mughabghab,G.P.A. Nobre,G. Palmiotti,A. Palumbo,M.T. Pigni,V.G. Pronyaev,R.O. Sayer,A.A. Sonzogni,N.C. Summers,P. Talou,I.J. Thompson,A. Trkov,R.L. Vogt,S.C. van der Marck,A. Wallner,M.C. White,D. Wiarda,P.G. Young.ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data[J].Nuclear Data Sheets.2011(12)
  • 2MCNP—A general Monte Carlo N-particle trans-port code:Version 5. LA-UR-03-1987 . 2003
  • 3Childs R L.SEN1:A one-dimensional cross-section sensitivity and uncertainty module for criticality safety analysis[]..1999
  • 4Mac Farlane R E,Muir D W.NJOY99.0,code system for producing pointwise and multigroup neutron and photon cross sections from ENDF/B data[].Los Alamos National LaboratoryLA--M.2000

共引文献1

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