严重事故下大功率先进压水堆IVR-ERVC有效性分析

发布时间：2018-01-02 11:47

本文关键词：严重事故下大功率先进压水堆IVR-ERVC有效性分析　出处：《核科学与工程》2016年01期 　论文类型：期刊论文

【摘要】：通过压力容器外部冷却(ERVC)以实现堆内熔融物滞留(IVR)作为反应堆严重事故缓解管理的一项重要举措一直以来广泛受到关注和研究。本文使用严重事故分析程序MELCOR,从瞬态角度对大型先进压水堆进行了IVR-ERVC相关研究。过程中重点关注了堆芯熔毁和重新定位,熔池形成、生长及其传热过程,并且对压力容器外部流动传热进行了分析。MELCOR计算所得下封头热流密度分布的瞬态结果与临界热流密度(CHF)比较和分析表明,1700 MWe大功率压水堆发生严重事故后在IVRERVC条件下能够保证压力容器的完整性,即,IVR-ERVC能够有效带出下封头熔融物的衰变热量,缓解严重事故后果。
[Abstract]:Retention of molten matter in reactor by external cooling of pressure vessel ERVC). As an important measure of reactor accident mitigation management, it has been widely concerned and studied. In this paper, MELCOR is used to analyze the serious accident. From the transient point of view, the IVR-ERVC research on the large-scale advanced PWR is carried out. In the process, the core melting and repositioning, the formation of the molten pool, the growth and the heat transfer process are focused on. The transient results of the heat flux distribution of the lower head calculated by MELCOR are compared with that of the critical heat flux (CHF). The integrity of pressure vessel can be guaranteed under the condition of IVRERVC after the serious accident of 1700 MWe high power PWR. IVR-ERVC can effectively bring out the decay heat of the lower head melt, and alleviate the serious accident consequences.
【作者单位】：上海交通大学;国核科学技术研究院;
【分类号】：TL364.4
【正文快照】： ivr-ervc 进核能反麟歐imM分前}0SM的严重事故缓解,例如美国设计的AP600,AP1000型压水堆[1’2’6],韩国设计的APR1400型压水堆[7]等。IVR-ERVC亦将成为中国未来先进核能反应堆安全设计的选择之一。目前,中国自主设计的CAP1400型反应堆已采用该技术,而正在设计中的更大型压水

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