Properties of a Prototype Corium of Nuclear Reactor

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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Veröffentlicht in:Science and Technology of Nuclear Installations 2018-01, Vol.2018 (2018), p.1-7
Hauptverfasser: Batyrbekov, Erlan G., Deryavko, Ilya I., Mukhamedov, Nurzhan Ye, Skakov, Mazhyn K.
Format: Artikel
Sprache:eng
Schlagworte:
Alloys
Analysis
Crystallography
Design
Experiments
Heat
High temperature
Laboratories
Nuclear accidents
Nuclear energy
Nuclear engineering
Nuclear facilities
Nuclear reactors
Phase composition
Physical instruments
Prototypes
Stainless steel
Studies
Thermal conductivity
Thermal diffusivity
Thermal properties
Thermophysical properties
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Beschreibung
Zusammenfassung: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
DOI:10.1155/2018/5208510