Creep Evaluation for a PWR Reactor Pressure Vessel Lower Head Under Severe Accident Conditions Considering Sustained Internal Pressure

Yongjian Gao, M. Cao, Yinbiao He
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引用次数: 1

Abstract

In-Vessel Retention (IVR) is one of appropriate severe accident mitigation strategies for AP1000 Nuclear Power Plant (NPP), and assurance of prevention against to thermal failure and structural failure of Reactor Pressure Vessels (RPV) is the prerequisite of IVR. A Finite Element Model fora RPV considering lower head melting was established, the creep calculation was carried out after the temperature field analysis, and the stress-strain responses for different times were obtained. By means of choosing representative evaluation sections and applying the Accumulative Damage Theory based on Larson-Miller Parameter, the Creep Damage calculations and evaluations were conducted. The results showed that the failure modes associated with creep rupture would not happen under IVR condition when a certain amount of internal pressure sustained. The approaches employed in this paper could be utilized in structural integrity evaluation of RPV under IVR for other new type NPPs.
考虑持续内压的严重事故条件下压水堆压力容器下压头蠕变评价
IVR (In-Vessel Retention)是适用于AP1000核电站的严重事故缓解策略之一,保证反应堆压力容器(RPV)的热失效和结构失效是IVR的前提。建立了考虑下头熔化的RPV有限元模型,在温度场分析后进行了蠕变计算,得到了不同时间的应力应变响应。通过选取具有代表性的评价断面,应用基于Larson-Miller参数的累积损伤理论,进行了蠕变损伤计算与评价。结果表明:在一定的内压条件下,在IVR条件下不会出现蠕变破裂相关的破坏模式;本文所采用的方法可用于其他新型核电站在IVR下的RPV结构完整性评估。
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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