Tritium release properties of neutron-irradiated Be12Ti

被引：30

作者：

Uchida, M ^{[1
]}

Ishitsuka, E ^{[1
]}

Kawamura, H ^{[1
]}

机构：

[1] Japan Atom Energy Res Inst, Oarai Res Estab, Oarai, Ibaraki 3111394, Japan

来源：

JOURNAL OF NUCLEAR MATERIALS | 2002年 / 307卷 / 1 SUPPL.期

关键词：

D O I：

10.1016/S0022-3115(02)01219-9

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Be12Ti has a high melting point and good chemical stability and is a promising advanced material for the neutron multiplier of the DEMO reactor that requires temperatures higher than 600 degreesC in a blanket. To evaluate the tritium inventory in the breeding blanket, a tritium release experiment of neutron-irradiated Be12Ti with a total fast fluence of about 4 x 10(20) n/cm(2) (E > 1 MeV) was carried out at 330, 400 and 500 degreesC. It was clear that tritium could be released easier than from beryllium, and the apparent diffusion coefficient in Be12Ti was about two orders larger than that in beryllium at 600-100 degreesC. In addition to the good tritium release property, the swelling calculated from the density change of the specimens up to 1100 degreesC in this test was smaller than that of beryllium. (C) 2002 Elsevier Science B.V. All rights reserved.

引用

页码：653 / 656

页数：4