期刊文献+

核反应堆物理确定论计算程序系统NECP软件包的研发与应用 被引量:2

Development and Application of NECP Code Package of Deterministic Nuclear Reactor Physics Code System
下载PDF
导出
摘要 NECP软件包是西安交通大学反应堆物理团队开发的确定论核反应堆物理计算程序系统,软件包包括自主化的NECP-Atlas、Bamboo、X和SARAX程序。NECP软件包经过了大量的验证与确认。数值结果表明,NECP软件包精度高,可满足不同反应堆物理计算需求,具有高度的通用性并实现了对压水堆的高保真建模和计算。目前程序已应用于我国大型压水堆项目、示范快堆项目等重点工程。应用结果表明,NECP软件包已达到甚至优于国际先进核设计程序水平,对我国核电软件自主化和核设计能力提升具有重要的意义。 The NECP code package is a deterministic nuclear reactor physics code system developed by the Reactor Physics Team of Xi’an Jiaotong University.The NECP code package includes NECP-Atlas,Bamboo,X and SARAX codes.The code package was verified and validated by a large number of benchmarks and evaluated experiments.The numerical results show that the NECP code package has high precision and can meet the physics calculation requirements of different reactors.It has wide generality and realizes high fidelity modeling and simulation of pressurized water reactor.At present,the NECP code package was applied to several key projects such as large-scale pressurized water reactor project and demonstration fast reactor project in China.The application results show that the NECP code package reaches or even surpasses the level of other nuclear design codes abroad,and has great significance in Chinese code autonomy of nuclear power and improvement of nuclear design capability.
作者 吴宏春 曹良志 郑友琦 李云召 祖铁军 刘宙宇 WU Hongchun;CAO Liangzhi;ZHENG Youqi;LI Yunzhao;ZU Tiejun;LIU Zhouyu(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,China)
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2019年第10期1833-1841,共9页 Atomic Energy Science and Technology
基金 国家自然科学基金资助项目(11775169,11735011)
关键词 核反应堆物理 软件自主化 确定论方法 验证与确认 nuclear reactor physics code autonomy deterministic method verification and validation
  • 相关文献

参考文献4

二级参考文献14

  • 1臧明昌.第三代核电和西屋公司AP1000评述[J].核科学与工程,2005,25(2):106-115. 被引量:36
  • 2STAMM'LER R J J, ABBATE M J. Method of steady state reactor physics in nuclear design[J]. London, New York.. Academic Press, 1983.
  • 3CHETAINEA R, ERRAD S L. The use of the characteristics method to solve the transport equation in unstructured geometries [J]. Radia- tion Physics and Chemistry, 2001, 61 : 763-765.
  • 4KOSAKA S, SAJI E. Transport theory calcula- tion for a heterogeneous multi-assembly problem by characteristics method with direct neutron path linking technique[J]. Journal of Nuclear and Technology, 2000, 37(12): 1 015-1 023.
  • 5LIU Zhouyu, WU Hongchun, CAO Liangzhi, et al. A new three-dimensional method of character- istics for neutron transport calculation[J]. An- nals of Nuclear Energy, 2011, 38 : 447-454.
  • 6LEWIS E E, SMITH M A, TSOULFANIDIS N, et al. Benchmark specification for determinis- tic 2 D/3-D MOX fuel assembly transport calcu- lations without spatial homogenization (C5G7 MOX), NEA/NSC/DOC ( 2001 ) 4 [ R ] USA : OECD/NEA, 2001.
  • 7张宏博.基于区域分解的矩阵特征线方法及二维三维耦合中子学计算方法研究[D].西安:西安交通大学博士学位论文,2012.
  • 8陈其昌.任意几何特征线方法及其在直接循环堆组件计算中的应用研究[D].西安:西安交通大学博士学位论文,2010.
  • 9陈其昌,吴宏春,曹良志.基于AutoCAD二次开发技术的任意几何中子输运方程特征线方法[J].原子能科学技术,2008,43(3):79-84.
  • 10Lewis E E, Smith M A, Tsoulfanidis N, et al. Benchmark on Deterministic Transport Calculations Without Spatial Homogenisation[R]. OECD/NEA, 2003.

共引文献9

同被引文献13

引证文献2

二级引证文献3

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