The main structural-phase states of interaction between model corium of a nuclear reactor and a sacrificial material based on Al2O3 and a lead layer

M.K. Skakov , V.V. Baklanov , I.M. Kukushkin , M.K. Bekmuldin , A.S. Akaev , M.N. Azbergenov , A.V. Gradoboev
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Abstract

This article presents the results of post-experimental studies of the interaction of model light water reactor corium with a candidate sacrificial material (SM) based on Al2O3 (corundum) and a lead layer. The purpose of the experiments was to study the features of the interaction of the sacrificial material with corium in the conditions of simulating a severe accident with core meltdown. An active interaction of corium with the sacrificial material was established as a result of the research. This is confirmed by the fact that part of the sacrificial material entered into physical and chemical interaction with the components of corium with the formation of liquid-phase reaction products and, as a result, creating different conditions for the crystallization of corium. The study of the phase composition showed that the microstructure of solidified corium in various areas after interaction with the sacrificial material is represented by a phase of the (U,Zr, …)O2±x type with different types of crystal lattice. At the same time, the phase analysis showed a close correspondence of the composition of the solid solutions to the initial ratio of uranium and zirconium in the model corium charge. This allows us to conclude that liquid zirconium interacted with aluminum oxide during the experiment. Thus, it was concluded that the proposed sacrificial material is promising based on the results obtained and the identified features of the interaction of aluminum oxide with the lead layer and the corium of a nuclear reactor.

核反应堆模型铈与基于氧化铝和铅层的牺牲材料之间相互作用的主要结构相态
本文介绍了对模型轻水反应堆冕与基于氧化铝(刚玉)和铅层的候选牺牲材料(SM)之间相互作用的实验后研究结果。实验的目的是研究在模拟堆芯熔毁严重事故的条件下,牺牲材料与冕的相互作用特征。研究结果表明,铈与牺牲材料之间存在积极的相互作用。部分牺牲材料与冕成分发生了物理和化学作用,形成了液相反应产物,从而为冕的结晶创造了不同的条件,这一事实证实了这一点。对相组成的研究表明,在与牺牲材料相互作用后的不同区域,凝固铈的微观结构表现为具有不同晶格类型的(U,Zr,...)O2±x 型相。同时,相分析表明,固溶体的组成与模型铈电荷中铀和锆的初始比例密切相关。由此我们可以得出结论,液态锆在实验过程中与氧化铝发生了相互作用。因此,根据所获得的结果以及氧化铝与铅层和核反应堆铈相互作用的特征,可以得出结论,所提议的牺牲材料是有前途的。
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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