Microstructure and mechanical properties of the LWR solidified melt prototype obtained by the out-of-pile experiment
Mukhamedov N.Y. Tskhe V.K. Sapatayev Y.Y. Kukushkin I.M.
1 December 2021Elsevier Ltd
Annals of Nuclear Energy
2021#163
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.
Corium , Melt , Microstructure , Reactor core
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“Institute of Atomic Energy” Branch RSE NNC RK, Kurchatov, Kazakhstan
D. Serikbayev East Kazakhstan Technical University, Ust-Kamenogorsk, Kazakhstan
“Institute of Atomic Energy” Branch RSE NNC RK
D. Serikbayev East Kazakhstan Technical University
10 лет помогаем публиковать статьи Международный издатель
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