INVESTIGATIONS ON SWELLING AND FISSION-GAS BEHAVIOR IN URANIUM-DIOXIDE

被引：62

作者：

ZIMMERMANN, H

机构：

[1] Kernforschungszentrum Karlsruhe, Institut für Material- and Festkörperforschung, Postfach 3640

来源：

JOURNAL OF NUCLEAR MATERIALS | 1978年 / 75卷 / 01期

关键词：

D O I：

10.1016/0022-3115(78)90039-9

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

UO2 irradiated at temperatures between 1000 and 2100 K was investigated with respect to fission gas behaviour and swelling. The amount of fission gas was measured in three steps as released fission gas, fission gas retained in bubbles and pores, and fission gas in the fuel matrix. The retained fission gas reaches concentrations up to 1.6 × 10-2 gas atoms per uranium atom at temperatures below 1250 K and decreases with increasing temperature. The swelling was evaluated by measuring the volume changes and by immersion density measurements. The maximum fission gas swelling without extensive bubble migration is about 20% at 2000 K. It diminishes to about 5% at 1250 K. © 1978.

引用

页码：154 / 161

页数：8

共 9 条

[1] CONTINUOUS MEASUREMENT OF LEAKAGE OF UO2 UNDER IRRADIATION [J].