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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Series: | Science and Technology of Nuclear Installations |
Online Access: | http://dx.doi.org/10.1155/2018/5208510 |
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doaj-8d748ed811554f6fa61f1fdb3a1a731a2020-11-24T23:49:18ZengHindawi LimitedScience and Technology of Nuclear Installations1687-60751687-60832018-01-01201810.1155/2018/52085105208510Properties of a Prototype Corium of Nuclear ReactorMazhyn K. Skakov0Nurzhan Ye. Mukhamedov1Ilya I. Deryavko2Erlan G. Batyrbekov3Institute of Atomic Energy, RSE NNC RK, Kurchatov, 071100, KazakhstanInstitute of Atomic Energy, RSE NNC RK, Kurchatov, 071100, KazakhstanInstitute of Atomic Energy, RSE NNC RK, Kurchatov, 071100, KazakhstanNational Nuclear Center RK, Kurchatov, 071100, KazakhstanThe 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.http://dx.doi.org/10.1155/2018/5208510 |
collection |
DOAJ |
language |
English |
format |
Article |
sources |
DOAJ |
author |
Mazhyn K. Skakov Nurzhan Ye. Mukhamedov Ilya I. Deryavko Erlan G. Batyrbekov |
spellingShingle |
Mazhyn K. Skakov Nurzhan Ye. Mukhamedov Ilya I. Deryavko Erlan G. Batyrbekov Properties of a Prototype Corium of Nuclear Reactor Science and Technology of Nuclear Installations |
author_facet |
Mazhyn K. Skakov Nurzhan Ye. Mukhamedov Ilya I. Deryavko Erlan G. Batyrbekov |
author_sort |
Mazhyn K. Skakov |
title |
Properties of a Prototype Corium of Nuclear Reactor |
title_short |
Properties of a Prototype Corium of Nuclear Reactor |
title_full |
Properties of a Prototype Corium of Nuclear Reactor |
title_fullStr |
Properties of a Prototype Corium of Nuclear Reactor |
title_full_unstemmed |
Properties of a Prototype Corium of Nuclear Reactor |
title_sort |
properties of a prototype corium of nuclear reactor |
publisher |
Hindawi Limited |
series |
Science and Technology of Nuclear Installations |
issn |
1687-6075 1687-6083 |
publishDate |
2018-01-01 |
description |
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. |
url |
http://dx.doi.org/10.1155/2018/5208510 |
work_keys_str_mv |
AT mazhynkskakov propertiesofaprototypecoriumofnuclearreactor AT nurzhanyemukhamedov propertiesofaprototypecoriumofnuclearreactor AT ilyaideryavko propertiesofaprototypecoriumofnuclearreactor AT erlangbatyrbekov propertiesofaprototypecoriumofnuclearreactor |
_version_ |
1725482967836393472 |