期刊文献+

全厂断电时安全壳直接加热的概率研究

Study on containment direct heating probability in station blackout
在线阅读 下载PDF
导出
摘要 安全壳直接加热(DCH)是导致安全壳早期失效的潜在因素,本文应用基于风险导向的事故分析方法(ROAAM),对堆芯碎片中UO_2的质量和Zr的氧化份额的概率密度分布抽样,对安全壳直接加热模型TCE(Two-cell Equilibrium)编程,将抽样结果带人TCE模型中计算,得到安全壳压力峰值的累积概率分布和安全壳失效概率,研究压水堆全厂断电始发事故下轴封破口面积不同的情况对下封头失效后安全壳压力峰值的影响。其中TCE模型的输入数据由严重事故分析程序计算给出。 Containment direct heating (DCH)is a potential factor which may cause early failure of containment. In this paper, containment peak pressure and containment failure probability in DCH process are assessed by Risk-Oriented Accident Analysis Methodology (ROAAM)using Two-Cell Equilibrium (TCE)model. The influence of the diameter length of seal-LOCA in Station Blackout (SBO )in reference plant is also analyzed. In ROAAM,probability distribution for Zirconium oxidation fraction and UO2 mass in core debris are sampled to calculate as part of the input data of TCE model. The other part of the input data of the TCE model is given by severe accident analysis program.
出处 《核科学与工程》 CAS CSCD 北大核心 2016年第2期172-177,共6页 Nuclear Science and Engineering
关键词 安全壳直接加热 安全壳失效概率 TCE模型 ROAAM Containment direct heating Containment failure probability ROAAM TCE model
作者简介 陈阳丽(1992-),女,满族,辽宁人,中国科学技术大学核科学技术学院硕士生,现主要从事反应堆热工与安全研究
  • 相关文献

参考文献6

  • 1M.M. Pileh, H. Yan, T. G. Theofanous. The Probability of Containment Failure by Direct Containment Heating in Zion [R]. NUREG/CR-6075 SAND93-1535, U.S., July, 1994: 195-241.
  • 2M.M. Pilch, M. D. Allen, K. D. Spencer. The Probability of Containment Failure by Direct Containment Heating in Surry [R]. NUREG/CR-6109 SAND93-2078, U.S., May 1995: 10-35.
  • 3张琨.核电厂安全壳直接加热相关法规及分析方法研究[J].核标准计量与质量,2012(3):16-21. 被引量:2
  • 4M.M. Pilch, M. D. Allen and R. O. Griffith Kinetic Limitations to Adiabatic Equilibrium Models for Direct Containment Heating (DCH) [C]. 28th ASME/AICHE/ ANS National Heat Transfer Conference, San Diego, 1992.
  • 5J.H. Scobel, T. G. Theofanous, S. W. Sorrell. Appli- cation of the risk oriented accident analysis methodology (ROAAM) to severe accident management in the AP600 advanced light water reaetor[J]. Reliability Engineering System Safety, Volume 62, Issues 1-2, October- November, 19981 51-58.
  • 6林继铭,陈鹏,张世顺.CPRl000核电厂安全壳超压失效概率及过滤排放系统改进研究[c].核动力厂严重事故管理研讨会,2009:16-21.

二级参考文献6

  • 1NRC.Individual plant examina-tion(IPE)for severe accident vulnerabilities-10[].CFR (f).1988
  • 2Evolutionary Light Water Reactor (LWR) Certification Issues and their Relationship to Current Regulatory Requirements. SECY-90-016 . 1990
  • 3Policy,Technical,and Licensing Issues Pertaining to Evolutionary and Advanced Light-water Reactor (ALWR)Designs. SECY-93-087 . 1993
  • 4Rohde J.O,Bari R.A,Morris B.W.Status of Direct Containment Heating in CSNI Member Coun-tries[].NEA/CSNI/R.1989
  • 5.High-pressure Melt Ejec-tion (HPME)and Direct Containment Heating (DCH)[].NEA/CSNI/R.1996
  • 6Design of Reactor Containment Sys-tems for Nuclear Power Plants. NS-G-1.10 . 2004

共引文献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