Cracking of a nuclear waste container material by irradiation in a simulated groundwater

被引：1
|
作者：
James, L.A. [1 ]
机构：
[1] Westinghouse Electric Corp., West Mifflin, PA 15122, United States
来源：
Nuclear and Chemical Waste Management | 1988年 / 8卷 / 01期
关键词：
CONTAINERS - Radiation Effects - STEEL - Crack Propagation - STEEL TESTING - Fatigue - WATER; UNDERGROUND;
D O I：
10.1016/0191-815X(88)90010-1
中图分类号：
学科分类号：
摘要：
Fatigue-crack propagation tests were conducted on a container material (ASTM A27 steel) tested in Hanford groundwater at 150 degree C for application in a potential basalt repository. Tests were run at a single value of stress intensity factor on groups of identical specimens undergoing gamma irradiation and control specimens not exposed to irradiation. The gamma flux levels (approx. 123 rad/hour) were prototypic of the maximum levels expected at the outer surface of the waste container. A statistical evaluation suggested that there were no significant differences between crack growth rates in the unirradiated and irradiated specimens.
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页码：75 / 82
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