NUCLEAR REACTOR CORIUM PROPERTIES OBTAINED AT IGR RESEARCH REACTOR
https://doi.org/10.52676/1729-7885-2019-1-129-132
Abstract
In the paper for the first time thermophysical properties (specific heat capacity, thermal diffusivity and thermal conductivity) of natural corium of a fast nuclear power reactor were determined in the temperature range from room one up to ~400 °С. The obtained data is oriented at use in temperature field calculations when modeling the processes of corium melt retention in fast nuclear reactor vessel.
About the Authors
M. K. Skakov
RSE NNC RK Branch “Institute of Atomic Energy”
Казахстан
Kurchatov
Казахстан
Kurchatov
N. Ye. Mukhamedov
RSE NNC RK Branch “Institute of Atomic Energy”
Казахстан
Kurchatov
Казахстан
Kurchatov
A. V. Pakhnits
RSE NNC RK Branch “Institute of Atomic Energy”
Казахстан
Kurchatov
Казахстан
Kurchatov
I. I. Deryavko
RSE NNC RK Branch “Institute of Atomic Energy”
Казахстан
Kurchatov
Казахстан
Kurchatov
References
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5. V. Zhdanov, V. Baklanov et al. The Methodology of Determining Heat-Transfer Properties of the Samples of Promising Fuel for Water-Moderated Water-Cooled Power Reactor // Proceedings of Intern. conf. “Nuclear Power of the Republic of Kazakhstan” June 11–13, 2008, Kurchatov, IAE NNC RK. – 2009. – pp. 150–156.
Review
For citations:
Skakov M.K., Mukhamedov N.Ye., Pakhnits A.V., Deryavko I.I. NUCLEAR REACTOR CORIUM PROPERTIES OBTAINED AT IGR RESEARCH REACTOR. NNC RK Bulletin. 2019;(1):129-132. (In Russ.) https://doi.org/10.52676/1729-7885-2019-1-129-132
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