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IVR Model Study for Passive PWR

机译:无源压水堆的IVR模型研究

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摘要

1000-MWe scale Pressurized Water Reactor (PWR) is taking service or under construction all over the world, and larger scale plant is studied and developed for its more competitive economics. Not only design basic accidents are analyzed for nuclear safety, the severe accident must also be considered to meet with the increasing requirement of safety. In the "nuclear power plant design safety regulation"(HAF102) issued by Nation Nuclear Safety Administration (NNSA), aim at the preventing and mitigating of severe accident, the regulation bring forward new requirement, which required that during design phase, NPP should consider setting the preventing and mitigation measurement of severe accident as actually as possible. As an approach to prevent the curium from melting down the vessel and entering the containment when a postulated severe accident occurs, In-vessel retention (IVR) of molten core debris via water cooling of the external surface of the reactor vessel has been introduced into API 000. External reactor vessel cooling (ERVC) is assumed to be achieved keeping exterior surface of vessel at 400K. It is known to all that different scenario and process results in different IVR molten model. As the core melt, different IVR model is formed at different time, such as two-layer model, three-layer model and four layer model. It is necessary to study the IVR model when severe accident process moves on. This paper studies two-layer and three-layer IVR models and find the features of the models. Based on this, sensitivity study of important parameters has also been analyzed. It is useful for us to understand the mechanism of the molten pool. This paper has some directive significance on future IVR strategy research and also provides theoretical support to safety evaluation of PWR plants.
机译:1000 MWe规模的压水堆(PWR)在全球范围内正在使用或在建,并且由于其更具竞争力的经济性,正在研究和开发规模更大的工厂。不仅要对设计基本事故进行核安全分析,还必须考虑严重事故,以满足不断增长的安全要求。在国家核安全局(NNSA)发布的“核电厂设计安全规程”(HAF102)中,针对预防和减轻严重事故,该规章提出了新的要求,要求在设计阶段,核电厂应考虑尽可能实际地设置严重事故的预防和缓解措施。作为防止假定的严重事故发生时cur熔化容器并进入安全壳的方法,已通过反应堆容器外表面的水冷将熔融堆芯碎屑的容器内滞留(IVR)引入了API中000.假定实现了反应堆外部容器冷却(ERVC),将容器的外表面保持在400K。众所周知,不同的场景和过程会导致不同的IVR熔融模型。随着核心融化,在不同时间形成不同的IVR模型,例如两层模型,三层模型和四层模型。当严重事故过程继续进行时,有必要研究IVR模型。本文研究了两层和三层IVR模型,并找到了模型的特征。在此基础上,还对重要参数的敏感性研究进行了分析。对于我们了解熔池的机制很有用。本文对未来的IVR策略研究具有一定的指导意义,并为压水堆电厂的安全性评估提供理论支持。

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