期刊文献+

采用概率方法确定严重事故下安全壳内环境条件的初步分析 被引量:2

Preliminary Analysis of Containment Condition under Server Accident Using PSA
下载PDF
导出
摘要 本文采用概率方法确定严重事故下安全壳内的环境条件。从而降低了对严重事故下所需设备的要求,使得设备的设计和采购更灵活,并具有一定的经济性。 The purpose of this article is to determine the containment condition under Server Accident using PSA for nuclear power plant.It will decrease the requirement of the equipment,and make the design of equipment more flexible.
作者 王喆
出处 《科技传播》 2012年第10期80-80,72,共2页 Public Communication of Science & Technology
关键词 概率 严重事故 环境条件 PSA,Server Accident,Containment Condition
  • 相关文献

参考文献3

二级参考文献12

  • 1Sandia National Laboratory.Severe accident risks:An assessment for five U.S.nuclear power plants,NUREG-1150[R].Washington D.C.,USA:NRC,1990.
  • 2KIM S D.An evaluation of a general venting strategy in a CANDU 6 reactor building[J].Annals of Nuclear Energy,2007,34:661-669.
  • 3NEA.Insights into the control of the release of iodine,cesium,strontium and other fission products in the containment by severe accident management,NEA/CSNI/R(2000)9[R].Le Seine,France:OECD NEA,2000.
  • 4NRC.Code manual for MACCS2,NUREG/CR-6613[R].Washington D.C.,USA:NRC,1998.
  • 5国家核安全局.HAF102,核动力厂设计安全规定[S].北京:周家核安全局,2004.
  • 6U.S. Nuclear Regulatory Commmsion Regulations. 10CFR50. Code of Federal Regulations [S]. U. S. NRC, 2006.
  • 7US Nuclear Regulatory Commissions, RG 1. 157, BestEstimate Calculations of Emergency Core Cooling System Performance[S]. U.S. NRC, May 1989.
  • 8Westinghouse LLC, Westinghouse AP1000 Design Control Document[ R]. Westinghouse Electirc Company LLC, 2008.
  • 9U.S. NRC. Final Safety Evaluation Report: Related to certification of the AP1000 standard design[R]. U.S. NRC, 2004.
  • 10T Wicket, et al. Report of the Uncertainty Methods Study for Advanced Best Estimate Thermal Hydraulic Code Applications[M]. 2 vols, Rep. NEA/CSNI R(97) 35. Paris: OECD, 1998.

共引文献27

同被引文献14

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