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Review of experimental study on melt pool natural convection behavior

机译:熔池自然对流行为的实验研究综述

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摘要

In a hypothetical severe accident that happens in a light water reactor (LWR), the melt pool could be formed in the lower plenum of reactor pressure vessel (RPV). Remaining these molten materials inside RPV and preventing further leakage of these melt materials from RPV are treated as one of the severe accident management methods. In this aspect, one of the key issues is that the heat transfer from melt pool to RPV wall should be less than the corresponding critical heat flux (CHF) outside the vessel. The natural convection behavior in melt pools plays an important role in determining the heat flux from the melt pool to the RPV wall. Up to now, various experiments have been conducted to study the internally heated natural convection behavior in melt pools. In 1970s, several experiments were conducted, and mainly investigated the mechanism of internally heated natural convection phenomena. After TMI-2 and Chernobyl-4 severe accidents, such kinds of experiments were conducted worldwide, mainly aimed to further investigate the melt pool natural convection behavior in the lower plenum and conduct the experiment closer to the prototypical condition that may happen in a hypothetical severe accident. Some of these experiments were used to provide the data for severe accident management method assessment of their corresponding reactor types, and to solve the problems that were found or not solved by previous experiments. Especially the COPRA (COrium Pool Research Apparatus) experiment, of which the test section was the full scale and nitrate salt of which the physical properties are close to the prototypical material was used as the simulant material, improved the theoretical knowledge of the transient and steady-state phases of melt pool natural convection behavior. However, there are still uncertain and unclear phenomena related to the natural convection behavior in internally heated melt pools. This paper mainly summaries the melt pool natural convection experiments chronologically, and then points out the main remaining issues regarding the natural convection behavior in the melt pools in the RPV lower plenum.
机译:在轻水反应堆(LWR)中发生的假设性严重事故中,熔池可能会在反应堆压力容器(RPV)的下部增压室内形成。将这些熔融材料保留在RPV内并防止这些熔融材料进一步从RPV泄漏是严重的事故管理方法之一。在这方面,关键问题之一是从熔池到RPV壁的热传递应小于容器外部相应的临界热通量(CHF)。熔池中的自然对流行为在确定从熔池到RPV壁的热通量方面起着重要作用。迄今为止,已经进行了各种实验来研究熔池中内部加热的自然对流行为。 1970年代,进行了几次实验,并主要研究了内部加热的自然对流现象的机理。在TMI-2和Chernobyl-4严重事故发生之后,此类实验在全球范围内进行,主要目的是进一步研究下气室中熔池的自然对流行为,并使实验更接近假想严重情况下可能发生的原型条件。事故。这些实验中的一些被用来提供数据,以评估相应反应堆类型的严重事故管理方法,并解决先前实验中发现或未解决的问题。特别是COPRA(CO池研究装置)实验(其测试部分为满刻度)和物理性能接近于原型材料的硝酸盐用作模拟材料,提高了瞬态和稳态的理论知识。态相的熔池自然对流行为。但是,仍然存在与内部加热熔池中自然对流行为有关的不确定和不清楚的现象。本文主要按时间顺序对熔池自然对流实验进行了总结,然后指出了RPV下气室中熔池自然对流行为的主要问题。

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