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Melting Temperatures and Thermal Conductivities of Corium Prepared from UO2 and Zircaloy-2

Published online by Cambridge University Press:  22 May 2012

Masato Kato ,
Teppei Uchida ,
Shun Hirooka ,
Masatoshi Akashi ,
Akira Komeno  and
Kyoichi Morimoto
Masato Kato
Affiliation:
Advanced Nuclear System Research and Development Directorate, Japan Atomic Energy Agency, 4-33, Muramastu, Tokai-mura, Ibaraki, 311-1194, Japan
Teppei Uchida
Affiliation:
Advanced Nuclear System Research and Development Directorate, Japan Atomic Energy Agency, 4-33, Muramastu, Tokai-mura, Ibaraki, 311-1194, Japan
Shun Hirooka
Affiliation:
Advanced Nuclear System Research and Development Directorate, Japan Atomic Energy Agency, 4-33, Muramastu, Tokai-mura, Ibaraki, 311-1194, Japan
Masatoshi Akashi
Affiliation:
Advanced Nuclear System Research and Development Directorate, Japan Atomic Energy Agency, 4-33, Muramastu, Tokai-mura, Ibaraki, 311-1194, Japan
Akira Komeno
Affiliation:
Advanced Nuclear System Research and Development Directorate, Japan Atomic Energy Agency, 4-33, Muramastu, Tokai-mura, Ibaraki, 311-1194, Japan
Kyoichi Morimoto
Affiliation:
Advanced Nuclear System Research and Development Directorate, Japan Atomic Energy Agency, 4-33, Muramastu, Tokai-mura, Ibaraki, 311-1194, Japan
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Abstract

Corium which simulates the molten core of a Boiling Water Reactor was prepared as a parameter of Zr content, and melting temperatures and thermal conductivities were measured. The melting temperatures were measured by the thermal arrest method and were 2622 oC, 2509 oC and 2540 oC, respectively, in the specimens of 24.3 at%, 49.0 at% and 73.5 at% Zr content. Thermal conductivities had low values of 2.0-3.5 W/m oC at temperatures of 400 to 1600 oC.

Keywords

nuclear materialsthermal conductivityphase equilibria
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1444: Symposium S/Y – Actinides and Nuclear Energy Materials , 2012 , mrss12-1444-y10-09
Copyright
Copyright © Materials Research Society 2012

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References

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