THE RELEASE OF FISSION-PRODUCTS FROM DEGRADED UO2 FUEL - THERMOCHEMICAL ASPECTS

被引：36
|
作者：
CORDFUNKE, EHP
KONINGS, RJM
机构：
[1] Netherlands Energy Research Foundation ECN, 1755 ZG Petten
来源：
JOURNAL OF NUCLEAR MATERIALS | 1993年 / 201卷
关键词：
D O I：
10.1016/0022-3115(93)90159-V
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
This review describes the chemical aspects of the release of the important fission products. Their behaviour in the fuel, in the reactor coolant system (primary system), and during core-concrete interactions, is discussed. Special attention is given to thermochemical modeling to incorporate the results of recent studies on the acquisition of thermochemical data for relevant species by experimental and evaluation techniques.
引用
收藏
页码：57 / 69
页数：13
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