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Melt quenching and coolability by water injection from below: Co-injection of water and non-condensable gas

机译:通过下面的注水进行熔体淬火和冷却性:水和不可冷凝气体的共注

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The interaction and mixing of high-temperature melt and water is the important technical issue in the safety assessment of water-cooled reactors to achieve ultimate core coolability. For specific advanced light water reactor (ALWR) designs, deliberate mixing of the core melt and water is being considered as a mitigative measure, to assure ex-vessel core coolability. The goal of our work is to provide the fundamental understanding needed for melt-water interfacial transport phenomena, thus enabling the development of innovative safety technologies for advanced LWRs that will assure ex-vessel core coolability. The work considers the ex-vessel coolability phenomena in two stages. The first stage is the melt quenching process and is being addressed by Argonne National Lab and University of Wisconsin in modified test facilities. Given a quenched melt in the form of solidified debris, the second stage is to characterize the long-term debris cooling process and is being addressed by Korean Maritime University via test and analyses. In this paper, experiments on melt quenching by the injection of water from below are addressed. The test section represented one-dimensional flow-channel simulation of the bottom injection of water into a core melt in the reactor cavity. The melt simulant was molten lead or a lead alloy (Pb-Bi). For the experimental conditions employed (i.e., melt depth and water flow rates), it was found that: (1) the volumetric heat removal rate increased with increasing water mass flow rate and (2) the non-condensable gas mixed with the injected water had no impairing effect on the overall heat removal rate. Implications of these current experimental findings for ALWR ex-vessel coolability are discussed.
机译:高温熔体和水的相互作用和混合是水冷反应堆安全性评估中实现最终堆芯可冷却性的重要技术问题。对于特定的先进轻水反应堆(ALWR)设计,考虑将堆芯熔体与水的故意混合作为缓解措施,以确保船外堆芯的可冷却性。我们工作的目的是提供融水界面传输现象所需的基本理解,从而为先进的轻水堆开发创新的安全技术,以确保船外堆芯的可冷却性。这项工作分两个阶段考虑了容器外的可冷却性现象。第一阶段是熔体淬火过程,阿贡国家实验室和威斯康星大学正在改进的测试设备中进行研究。考虑到凝固的碎片形式的淬火熔体,第二阶段将表征长期的碎片冷却过程,韩国海事大学正在通过测试和分析进行研究。在本文中,研究了通过从下方注入水进行熔体淬火的实验。测试部分代表了向反应器腔体中的底部熔体底部注水的一维流道模拟。熔融模拟物是熔融铅或铅合金(Pb-Bi)。对于所采用的实验条件(即熔体深度和水流率),发现:(1)体积排热率随着水质量流率的增加而增加;(2)与凝结水混合的不可凝气体对总的除热率没有影响。讨论了这些当前实验发现对ALWR容器冷却性的影响。

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