Beryllium neutron irradiation study in the Japan Materials Testing Reactor

被引：2
|
作者：
Ishitsuka, E [1 ]
Kawamura, H [1 ]
机构：
[1] Japan Atom Energy Res Inst, Oarai Res Estab, Oarai, Ibaraki 31113, Japan
来源：
FUSION ENGINEERING AND DESIGN | 1998年 / 41卷
关键词：
D O I：
10.1016/S0920-3796(98)00244-0
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
A beryllium irradiation study with the Japan Materials Testing Reactor of JAERI is reviewed from the point of view of tritium release, thermal properties, mechanical properties and reprocessing technology by using the neutron irradiated sample with a total fast neutron fluence up to 10(21) (n cm(-2)). It becomes clear that problems arise for each of the properties, for example, effects of the surface oxide layer, impurities, grain size, and/or swelling. Moreover, future plans of beryllium irradiation studies are discussed in this paper. (C) 1998 Elsevier Science S.A. All rights reserved.
引用
收藏
页码：195 / 200
页数：6
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