BWR Reactor Vessel Bottom Head Failure Modes

S. Hodge
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引用次数: 7

Abstract

Boiling water reactors (BWRs) incorporate many unique structural features that make their expected response under severe accident conditions very different from that predicted in the case of pressurized water reactor accident sequences. The effect of the BWR procedural and structural differences upon the progression of a severe accident sequence during the period preceding movement of core debris into the reactor vessel lower plenum has been discussed previously. It is the purpose of this paper to briefly address the events occurring after debris relocation past the core plate and to describe the subsequent expected modes of bottom head pressure boundary failure. As an example, the calculated timing of events for the unmitigated short-term station blackout severe accident sequence at the Peach Bottom Atomic Power Station is also presented. 14 refs., 4 figs., 1 tab.
沸水堆反应堆容器底部封头失效模式
沸水堆(BWRs)具有许多独特的结构特征,这使得沸水堆在严重事故条件下的预期响应与压水堆事故序列下的预期响应大不相同。沸水堆程序和结构上的差异对堆芯碎片进入反应堆容器下部静压室之前一段时间内严重事故序列进展的影响已经在前面讨论过。本文的目的是简要说明岩屑移动越过岩心板块后发生的事件,并描述随后的底压边界破坏的预期模式。并以桃底核电站非缓解短期电站停电严重事故序列为例,给出了事件时间的计算方法。14参。, 4个无花果。, 1页。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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