Steam-chemical reactivity for irradiated beryllium

被引：37

作者：

Anderl, RA ^{[1
]}

McCarthy, KA ^{[1
]}

Oates, MA ^{[1
]}

Petti, DA ^{[1
]}

Pawelko, RJ ^{[1
]}

Smolik, GR ^{[1
]}

机构：

[1] Lockheed Martin Idaho Technol Co, Idaho Natl Engn Lab, Fus Safety Program, Idaho Falls, ID 83415 USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 1998年 / 258卷

关键词：

D O I：

10.1016/S0022-3115(98)00255-4

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

This paper reports experimental results concerning the influence of neutron irradiation effects and annealing on the chemical reactivity of beryllium exposed to steam. The work entailed: (1) measurements of swelling, porosity and specific surface area for irradiated Be annealed at temperatures ranging from 700 degrees C to 1200 degrees C and (2) measurements of hydrogen generation rates for unirradiated Be, irradiated Be and irradiated-annealed Be exposed to steam at elevated temperatures. For irradiated Be, volumetric swelling increased from 14% at a 700 degrees C anneaI to about 56% at a 1200 degrees C anneal. Gas-release measurements during annealing indicated the development of a surface-collected porosity network. Specific surface areas for irradiated-annealed Be increased with the anneaI temperature. Steam-chemical reactivity was similar for irradiated and unirradiated Be at temperatures between 450 degrees C and 600 degrees C. For irradiated Be exposed to steam at 700 degrees C, the reactivity accelerated rapidly and the specimen experienced a temperature excursion. Irradiated-annealed Be showed enhanced chemical reactivity related to its higher specific surface area. (C) 1998 Elsevier Science B.V. All rights reserved.

引用

页码：750 / 756

页数：7

共 18 条

[1] TRITIUM AND HELIUM RELEASE FROM IRRADIATED BERYLLIUM [J].