THE METHOD OF CORIUM COOLING IN A CORE CATCHER OF A LIGHT-WATER NUCLEAR REACTOR

Q3 Engineering
М. Skakov
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引用次数: 1

Abstract

During the development of a severe accident at nuclearpower plantwith a core melting, corium is formed. One of the main barriers preventing outflow of corium into the environment is a melt localization device or a melt trap. The melt trap must accept and prevent the corium parameters from exceeding critical values, ensuring its retention in a controlled volume and cooling. For this reason, melt traps are subject to serious requirements regarding cooling methods to ensure effective containment of the melt in the core of a nuclear reactor. In the presented article, experimental studies of the interaction between corium and water, which was supplied to the surface of the corium in a melt trap for its cooling, were analyzed. As a result of the work, a number of significant problems associated with the low efficiency of this cooling method were identified, and possible ways to eliminate them were considered. A solution is proposed for optimizing the method of corium cooling in a melt trap, as well as for the scope of research on the possibility of implementing the proposed method in practice and analyzing its effectiveness using the VCG-135 test-bench and the Lava-B facility.
轻水反应堆堆芯捕集器冷却堆芯的方法
在核电站发生堆芯熔化严重事故的过程中,形成了堆芯。防止堆芯金属流出到环境中的主要障碍之一是熔体定位装置或熔体捕集器。熔体捕集器必须接受并防止堆芯参数超过临界值,确保其保持在受控的体积内并冷却。出于这个原因,熔体捕集器在冷却方法方面受到严格要求,以确保有效地将熔体容纳在核反应堆堆芯中。在本文中,分析了堆芯与水之间相互作用的实验研究,水被供应到熔化阱中的堆芯表面进行冷却。这项工作的结果是,发现了与这种冷却方法的低效率相关的许多重大问题,并考虑了消除这些问题的可能方法。提出了一种优化熔融阱中堆芯冷却方法的解决方案,以及在实践中实施所提出方法的可能性的研究范围,并使用VCG-135测试台和Lava-B设备分析其有效性。
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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来源期刊
CiteScore
1.10
自引率
0.00%
发文量
15
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