反应堆容器下封头屈曲强度及后屈曲行为研究

Masatoshi Murohara, A. Yamazaki, Takuya Sato, N. Kasahara
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引用次数: 0

摘要

从福岛第一核电站事故中吸取的教训,人们认识到控制事故后行为和减轻事故后果的重要性。传统的反应堆结构设计旨在防止由于设计基础事件(DBE)而导致的故障的发生。本研究旨在通过减轻失效后的后果,提高反应堆结构在超设计基础事件(BDBE)下的弹性,例如在严重事故期间的高温和过度地震。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Study on Buckling Strength and Post Buckling Behaviors of Reactor Vessel Lower Heads
As the lessons learned from the Fukushima Daiichi Nuclear Power Plant accident, the importance of controlling the behavior after a failure and mitigating consequences of a failure was recognized. Conventional reactor structural design has been aimed at preventing the occurrence of failure due to Design Basis Events (DBE). This study aims to improve the resilience of the reactor structure under Beyond Design Basis Events (BDBE), such as very high temperatures and excessive earthquakes during severe accidents, by mitigating the consequences after failure.
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