期刊文献+

全船断电叠加安全阀失效事故放射性释放分析 被引量:2

Analysis of accident due to interruption of power supply and safety valve failure
下载PDF
导出
摘要 针对全船断电叠加安全阀失效事故,以严重事故分析程序MELCOR为研究工具,建立了某型船用堆的分析模型,分析了稳压器安全阀在断电事故后开启1次、开启5次、开启13次后卡开失效及正常启闭4种工况。结果表明:安全阀开启1次后卡开失效事故进程最快,后果最严重;不卡开的情况,事故进程最慢;在安全阀开启13次以内的卡开失效时,各工况放射性物质释放至各部位的份额均比较接近,放射性后果的影响差别不大。 Aiming at the blackout accident, this paper presents a ship reactor model by use of the integration code of MELCOR. The model is used to analyze severe accidents. The analysis refers to four operating conditions: the pressurizer safe valve opening 1 time, 5 times, 13 times, and reiterative times. The result shows that the accident happens fastest and the aftereffect is the most serious after safe valve opens 1 time, and the accident happens slowest after the opening in reiterative times. When the safe valve opening is less than 13 times, the radioactive fraction is nearly the same in every situation and the radioactive aftereffect is not sensitive.
出处 《海军工程大学学报》 CAS 北大核心 2014年第6期37-41,共5页 Journal of Naval University of Engineering
基金 国家自然科学基金资助项目(11075212)
关键词 全船断电 MELCOR 安全阀 放射性 blackout-accident MELCOR safe valve radioactivity
  • 相关文献

参考文献6

二级参考文献15

  • 1陈松,刘鑫,史国宝,朱鑫官,蔡剑平.严重事故下安全壳内环境条件计算分析[J].核动力工程,2006,27(z1):13-17. 被引量:13
  • 2陈晓秋,岳会国,林权益.双层安全壳压水堆LOCA事故的放射性后果分析审查[J].辐射防护通讯,2005,25(4):1-8. 被引量:8
  • 3IQBAL M J, MIRZA N M, MIRZA S M. Kinetic simulation of fission product activity in primary coolant of typi- cal PWRs under power perturbations [J]. Nuclear Engineering and Design, 2007,237: 199--205.
  • 4LEWIS B J, EI-JABY A, HIGGS J, et al. A model for predicting coolant activity behavior for fuel-failure monito- ring analysis [J]. Journal of Nuclear Materials, 2007,366 : 37-- 51.
  • 5林晓玲,张贵文,孙培铨.船用反应堆堆芯放射性核素总量计算[J].海军工程学院学报,1997(4):55-59.
  • 6格拉希维里TB,赵志祥.核素数据手册[M].第3版.北京:原子能出版社,2004.
  • 7Oak Ridge National Laboratory. ORIGEN-ARP: Automatic Rapid Process for Spent Fuel Depletion, Decay, and Source Term Analysis [R]. Oak Ridge, Tennessee: NUREG/CR-0200,2000.
  • 8NRC.Methods and Assumptions for Evaluating Radiologi-cal Consequences of Design Basis Accidents at Light-waterNuclear Power Reactors Regulatory Guide 1.195[]..2003
  • 9Croff AG.A User○s Manualforthe ORIGEN2 ComputerCode[]..1980
  • 10.Determination of the in-containment source term for a large-break loss of coolant accident[].EN.2001

共引文献18

同被引文献8

引证文献2

二级引证文献5

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