Thermal conductivity of uranium-plutonium oxide fuel for fast reactors

被引：33
|
作者：
Inoue, M [1 ]
机构：
[1] Japan Nucl Cycle Dev Inst, Oarai Engn Ctr, Oarai, Ibaraki 3111393, Japan
来源：
JOURNAL OF NUCLEAR MATERIALS | 2000年 / 282卷 / 2-3期
关键词：
D O I：
10.1016/S0022-3115(00)00407-4
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
A new thermal conductivity correlation for fully dense uranium-plutonium oxide fuel for fast reactors was formulated for fuel pin thermal analysis under beginning of irradiation conditions. The data set used in correlating the equation was systematically selected to minimize experimental uncertainty. The electron conduction term for uranium dioxide formulated by Harding and Martin [J. Nucl. Mater. 166 (1989) 223] was adopted to compensate for so few high temperature measurements. The excellent predictability of the new correlation was validated by comparing the calculated with measured fuel center temperatures in an instrumented irradiation test in the experimental fast reactor JOYO for low oxygen-to-metal (O/M) ratio fuel up to 1850 K. (C) 2000 Elsevier Science B.V. All rights reserved.
引用
收藏
页码：186 / 195
页数：10
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