Properties of a Prototype Corium of Nuclear Reactor

The paper studies structure, phase composition, and thermophysical properties (TPP) (specific heat capacity, thermal diffusivity, and heat conductivity) of a prototype corium of a fast nuclear reactor (melt of core materials of nuclear reactor produced under out-of-pile conditions). The obtained dat...

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Bibliographic Details
Main Authors: Mazhyn K. Skakov, Nurzhan Ye. Mukhamedov, Ilya I. Deryavko, Erlan G. Batyrbekov
Format: Article
Language:English
Published: Hindawi Limited 2018-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2018/5208510
Description
Summary:The paper studies structure, phase composition, and thermophysical properties (TPP) (specific heat capacity, thermal diffusivity, and heat conductivity) of a prototype corium of a fast nuclear reactor (melt of core materials of nuclear reactor produced under out-of-pile conditions). The obtained data will be used to get more accurate understanding of main regularities of actual interaction of core materials of a nuclear reactor under a severe accident.
ISSN:1687-6075
1687-6083