期刊文献+

COSINE软件包堆芯物理分析程序(cosCORE)的初步验证 被引量:1

Preliminary Verification of COSINE Software Package Core Physical Analysis Program(cosCORE)
下载PDF
导出
摘要 COSINE软件包堆芯物理分析程序(cosCORE)是一款基于节块展开法的堆芯扩散程序。为了验证cosCORE对轻水堆模型的临界计算能力与组件功率计算能力,对三维两群压水堆问题IAEA_3D基准题与BSS-14基准题进行测试验证,并与基准值进行比对。结果显示,对于IAEA_3D基准题,cosCORE与基准值keff的相对误差为0.669‰,组件相对功率误差均小于2.178%;对于BSS-14基准题,计算值与基准值keff的相对误差为0.677‰,组件相对功率最大误差为1.7331%。 Core physical analysis program(cosCORE)of COSINE software package is a core diffusion code based on the nodal method.In order to verify the ability of critical calculation and assembly-wised power distribution calculation of cosCORE for the light water reactor model,the three-dimensional two-group pressurized water reactor problem IAEA_3D benchmark and BSS-14 benchmark were tested and verified,and compared with the benchmark value.The result shows that for the IAEA_3D benchmark,the relative error of k eff between cosCORE and the reference value is 0.669‰,and the error of relative assembly-wised power distribution is less than 2.178%;For BSS-14 benchmark,the relative error of k eff between the calculated value and the reference is 0.677‰,and the maximum error of the relative power density of the components is 1.7331%.
作者 苑旭东 周剑东 谢金森 陈珍平 郭倩 于涛 YUAN Xudong;ZHOU Jiandong;XIE Jinsen;CHEN Zhenping;GUO Qian;YU Tao(School of Nuclear Science and Technology,University of South China,Hengyang,Hunan 421001,China;Hunan Engineering & Technology Research Center for Virtual Nuclear Reactor,University of South China,Hengyang,Hunan 421001,China)
出处 《南华大学学报(自然科学版)》 2020年第4期7-12,共6页 Journal of University of South China:Science and Technology
基金 大型先进压水堆核电站国家科技重大专项项目(2017ZX06002002)。
关键词 COSINE软件包 IAEA_3D基准题 BSS-14基准题 测试验证 COSINE software package IAEA_3D benchmark BSS-14 benchmark test and verification
  • 相关文献

参考文献5

二级参考文献18

  • 1YANG Yanhua, CHEN Yixue, ZHANG Hao, et al. Requirement analysis and primary design of COSINE code[C]//ANS Annual Meeting. Chicago, USA: American Nuclear Society, 2012.
  • 2CHEN Yixue, YU Hui, LIU Zhanquan, et al. Development status of reactor physics codes in COSINE project[C]//The 18th Pacific Basin Nuclear Conference. Busan, Korea: KAIF and KNS, 2012.
  • 3刘占权.堆芯物理分析程序理论手册:V1.0[M].北京:国家核电软件技术中心,2011.
  • 4CHRISTENSEN B. Three dimensional static and dynamic reactor calculations by the nodal expansion method[R]. Denmark:Riso National Laboratory, 1998.
  • 5刘占权,王苏,胡啸字,等.堆芯物理分析程序理论手册V1.0[M].北京:国家核电技术有限公司北京软件技术中心,2011.
  • 6APIO00 design control document[M]. Westing- house: Westinghouse Electric Company LI.C, 2011.
  • 7BAHADIR T, LINDAHL S O, PALMTAG S P. Simulate-4 multigroup nodal code with micro- scopic depletion model[C] /// American Nuclear Society Topical Meeting in Mathematics & Com- putations. Avignon, France: LaGrange IL, 2005.
  • 8BAHADIR T, LINDAHL S O. Studsvik's next generation nodal code simulate 5 [C] // Advances in Nuclear Fuel Management IV. South Carolina: American Nuclear Society, LaGrange IL, 2009.
  • 9BOYD W A, MAYHUE L T, PENKROT V S, et al. The WHITESTAR development project: Westinghouse's next generation core design sim- ulator and core monitoring software to power the nuclear renaissance[C] // International Conference on Mathematics, Computational Methods & Re- actor Physics. New York: American Nuclear So- ciety, LaGrange IL, 2009.
  • 10STAMM'LER R J J, ABBATE M J. Methods of steady-state reactor physics in nuclear design[M]. [S. l. ]: Academic Press, 1983.

共引文献24

同被引文献36

引证文献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