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反应堆压力容器快中子注量计算方法研究 被引量:5

Development of the method for RPV fast neutron fluence calculation
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摘要 依据美国核管会有关压力容器中子注量确定方法的管理导则,在二维SN程序DORT的基础上,通过自行开发X-Y与R-θ坐标系间的中子源转换程序,建立起了一套基于综合法的压力容器三维快中子注量计算方法。NUREG/CR-6453和NUREG/CR-6115基准问题检验结果表明,本文所建立的方法能够提供满足工程精度要求的压力容器注量空间和能谱分布。 According to the NRC regulatory guide for determining pressure vessel neutron fluence, a synthesis method for obtaining the 3D fluence was developed based on the 2D SN code of DORT and a neutron source conversion code that maps the source from X-Y coordinate to R-O coordinate. Results of verification against the NUREG/CR-6453 and NUREG/CR-6115 benchmark problems demonstrated that the developed methodology is capable of providing neutron fluence spatial and energy spectrum distribution with acceptable accuracy.
出处 《核科学与工程》 CSCD 北大核心 2012年第4期289-294,共6页 Nuclear Science and Engineering
关键词 DORT 压力容器 快中子注量 基准题 DORT RPV fast neutron fluence benchmark problem
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参考文献6

  • 1Regulatory Guide 1. 190. Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluenee. U. S. Nuclear Regulatory Commission[D]. Office of Nuclear Regulatory Research, March 2001. 被引量:1
  • 2Rhoades W A, Childs R L. The DORT Two- Dimensional Discrete Ordinates Transport Code [J]. Nucl. Sci. & Engr. 1988,99(1):88-89. 被引量:1
  • 3RSIC Data Library Collection DLC-185, BUGLE-96, Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications [D]. March 1996. 被引量:1
  • 4ASTM Standards E482-01, Application of neutron transport methods for reactor vessel surveillance [D]. 2001. 被引量:1
  • 5Remec I, Kam F B K H B. Robinson-2 Pressure Vessel Benchmark[P]. NUREG/CR-6453, October 1997. 被引量:1
  • 6Carew J F, et al. PWR and BWR Pressure Vessel Fluence Calculation Benchmark Problems and Solutions. Broukhaven National Laboratory [P]. NUREG/CR- 6115, 2001. 被引量:1

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