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全厂断电引发的严重事故中反应堆压力容器失效机理研究 被引量:3

Study on Failure Principle of Reactor Pressure Vessel in Severe Acident Induced by Station Blackout
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摘要 以国际上典型的第2代3环路压水堆核电站为研究对象,采用严重事故最佳估算程序RELAP/SCDAPSIM,对全厂断电引发的严重事故中反应堆压力容器失效机理进行了计算分析。计算结果表明,RELAP/SCDAPSIM程序中的COUPLE二维有限元模型能够详细地预测压力容器内熔融物的行为特性,所给出的下封头失效时间和失效位置与已有实验结果吻合。 The reference plant was a typical three-loop PWR of generationⅡ,based on the best estimate computer code RELAP/SCDAPSIM,the failure principle of reactor pressure vessel in severe accident induced by station blackout was analysed.The calculation results show that RELAP/SCDAPSIM program of the COUPLE two-dimensional finite element model can predict the detailed molten material behavior characteristic in pressure vessel,and the lower head failure time and failure position are in good agreement with existing experimental results.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2012年第B09期305-308,共4页 Atomic Energy Science and Technology
基金 海军工程大学青年基金资助项目(HGDQNJJ014)
关键词 全厂断电 严重事故 反应堆压力容器 下封头 station blackout severe accident reactor pressure vessel lower head
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  • 1VIEROW K, LIAO Y, JOHNSON J, et al. Severe accident analysis of a PWR station black- out with the MELCOR, MAAP4 and SCDAP/ RELAP5 code[J]. Nuclear Engineering and De- sign, 2004, 234(1-3): 129-145.
  • 2KNUDSON D L, REMPE J L, CONDIE K G, et al. Late-phase melts conditions affecting the potential for in-vessel retention in high power re- actors [J]. Nuclear Engineering and Design, 2004, 230(1-3): 133-150.
  • 3SEHGAL B R, KARBOJ1AN A, GIRI A, et al. Assessments of reactor vessel integrity (ARVI) [J]. Nuclear Engineering and Design, 2005, 235 (23-53) : 213-232.

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