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4724287 
Journal Article 
Thermal properties of prototype corium of fast reactor 
Mukhamedov, N; Skakov, M; Deryavko, I; Kukushkin, I 
2017 
1 
Nuclear Engineering and Design
ISSN: 0029-5493
EISSN: 1872-759X 
322 
27-31 
WOS:000411468800003 
The paper is devoted to development and testing of a technology to manufacture the ingot of the prototype corium (resulted from out-of-pile conditions) of fast reactor followed by an experimental determination of the thermophysical properties (TP) (thermal diffusivity a, specific heat capacity C-p, and thermal conductivity lambda) of such corium at the room temperature (298 K). The data on the thermo-physical properties of corium (melt of structural and fuel materials of the reactor core) will be used to calculate the temperature fields in the modeling the processes of keeping corium inside the power reactor vessel under the conditions of a severe accident. (C) 2017 Elsevier B.V. All rights reserved. 
Prototype corium of a nuclear reactor; Thermophysical properties; Melting crucible; Material carbonization; Uranium dioxide; Stainless steel 
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