碎片床中铈池的可冷却性：碎片大小、蒸汽和液体流速、倾斜角度和压力对临界热通量的影响--首次数值评估

IF 1.2 3区工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Science and Engineering Pub Date : 2024-06-20 DOI:10.1080/00295639.2024.2357943

C. Sartoris, J.-A. Zambaux, F. Fichot

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引用次数: 0

摘要

在轻水反应堆发生严重事故时，堆芯中可能会形成碎片层，并有可能熔化，三里岛 2 号机组就曾发生过这种情况。有关这种熔融堆芯的可冷却性的知识...

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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Coolability of a Corium Pool in a Debris Bed: Impact of Debris Size, Steam, and Liquid Flow Rate; Tilting Angle; and Pressure on Critical Heat Flux—First Numerical Evaluations

In case of a severe accident in a light water reactor, a debris bed may form in the core and possibly melt, as happened in Three Mile Island Unit 2. Knowledge about the coolability of such a molten...

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来源期刊

Nuclear Science and Engineering 工程技术-核科学技术

CiteScore

2.10

自引率

25.00%

发文量

审稿时长

3 months

期刊介绍： Nuclear Science and Engineering, the research journal of the American Nuclear Society, publishes articles on research and development related to peaceful utilization of nuclear energy, radiation, and alternative energy sources.