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Thermal expansion of corium prepared from UO2 and Zircaloy-2

Published online by Cambridge University Press:  24 May 2012

Shun Hirooka ,
Masatoshi Akashi ,
Teppei Uchida ,
Kyoichi Morimoto  and
Masato Kato
Shun Hirooka
Affiliation:
Japan Atomic Energy Agency, 319-1194 Muramatsu, Tokai-mura, Naka-gun, Ibaraki-ken, Japan
Masatoshi Akashi
Affiliation:
Japan Atomic Energy Agency, 319-1194 Muramatsu, Tokai-mura, Naka-gun, Ibaraki-ken, Japan
Teppei Uchida
Affiliation:
Japan Atomic Energy Agency, 319-1194 Muramatsu, Tokai-mura, Naka-gun, Ibaraki-ken, Japan
Kyoichi Morimoto
Affiliation:
Japan Atomic Energy Agency, 319-1194 Muramatsu, Tokai-mura, Naka-gun, Ibaraki-ken, Japan
Masato Kato
Affiliation:
Japan Atomic Energy Agency, 319-1194 Muramatsu, Tokai-mura, Naka-gun, Ibaraki-ken, Japan
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Abstract

In this study, sintered pellets were prepared from Zircaloy-2 oxide and UO2 as a parameter of content ratio (Zr contents were 0, 24.3, 49.0, 73.4, and 97.9 at% in metal). The sintered pellets were heated in 5%H2/Ar gas. UO2 pellets underwent simple thermal expansion caused by thermal vibration while Zircaloy-2 oxide pellets underwent thermal expansion and volume change with phase transformation. Finally, the 24.3, 49.0, and 73.5 at%Zr-UO2 pellet specimens showed both phenomena. However, phase transformation temperatures were lower than that of Zircaloy-2 oxide, and volume changes were much smaller. X-ray diffraction patterns obtained after thermal expansion measurements showed that the 24.3 at%Zr-UO2 specimen contained tetragonal and cubic (Zr, U)O2 while the 73.5 at%Zr-UO2 specimen contained mainly monoclinic ZrO2.

Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1444: Symposium S/Y – Actinides and Nuclear Energy Materials , 2012 , mrss12-1444-y10-08
Copyright
Copyright © Materials Research Society 2012

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