A pragmatic approach to modelling thermal conductivity of irradiated UO2 fuel: Review and recommendations

被引：240

作者：

Lucuta, PG ^{[1
]}

Matzke, H ^{[1
]}

Hastings, IJ ^{[1
]}

机构：

[1] COMMISS EUROPEAN COMMUNITIES,JOINT RES CTR,INST TRANSURANIUM ELEMENTS,D-76125 KARLSRUHE,GERMANY

来源：

JOURNAL OF NUCLEAR MATERIALS | 1996年 / 232卷 / 2-3期

关键词：

D O I：

10.1016/S0022-3115(96)00404-7

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The thermal conductivity of irradiated UO2 fuel is discussed considering the effects of burnup (dissolved and precipitated solid fission products), porosity and fission-gas bubbles, deviation from stoichiometry; and radiation damage based on single-effect results previously published on SIMFUEL (simulated extended burnup UO2 fuel) and on radiation damage measurements. An analytical expression including factors describing the above effects is applied to the expression for unirradiated UO2 thermal conductivity; it reflects the knowledge available today, and It Is recommended for use with irradiated fuel. The expression is validated against available published data on thermal conductivity of irradiated fuel. This expression can bi incorporated into fuel modelling codes io improve calculations of operating temperatures and predictions of behaviour of irradiated fuel under normal and accident conditions, including the extended burnup.

引用

页码：166 / 180

页数：15