Removing the solidified core melt from damaged reactors by drilling or cutting requires knowledge of both mechanical properties and its microstructure. The ingot of the light-water power reactor prototype corium with a different blend composition containing ZrO₂, UO₂ and Zr was obtained in this work. The microstructure has been studied and the mechanical properties of the light-water power reactor core solidified melt materials have been determined. All samples showed typical brittle fracture behavior.

中文翻译：

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堆外实验得到的LWR凝固熔体原型的显微组织和力学性能

通过钻孔或切割从损坏的反应堆中取出凝固的核心熔体需要了解机械性能及其微观结构。在这项工作中获得了具有不同混合成分的轻水动力反应堆原型钴锭，其中含有 ZrO ₂、UO ₂和 Zr。对轻水动力堆堆芯固化熔融材料的微观结构进行了研究，并确定了其力学性能。所有样品都显示出典型的脆性断裂行为。