{"title":"核废料容器材料在模拟地下水中的辐照开裂","authors":"Lee A. James","doi":"10.1016/0191-815X(88)90010-1","DOIUrl":null,"url":null,"abstract":"<div><p>Fatigue-crack propagation tests were conducted on a candidate container material (ASTM A27 steel) tested in Hanford groundwater at 150°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.</p></div>","PeriodicalId":100966,"journal":{"name":"Nuclear and Chemical Waste Management","volume":"8 1","pages":"Pages 75-82"},"PeriodicalIF":0.0000,"publicationDate":"1988-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0191-815X(88)90010-1","citationCount":"2","resultStr":"{\"title\":\"Cracking of a nuclear waste container material by irradiation in a simulated groundwater\",\"authors\":\"Lee A. James\",\"doi\":\"10.1016/0191-815X(88)90010-1\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>Fatigue-crack propagation tests were conducted on a candidate container material (ASTM A27 steel) tested in Hanford groundwater at 150°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.</p></div>\",\"PeriodicalId\":100966,\"journal\":{\"name\":\"Nuclear and Chemical Waste Management\",\"volume\":\"8 1\",\"pages\":\"Pages 75-82\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"1988-01-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"https://sci-hub-pdf.com/10.1016/0191-815X(88)90010-1\",\"citationCount\":\"2\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear and Chemical Waste Management\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/0191815X88900101\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear and Chemical Waste Management","FirstCategoryId":"1085","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/0191815X88900101","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
Cracking of a nuclear waste container material by irradiation in a simulated groundwater
Fatigue-crack propagation tests were conducted on a candidate container material (ASTM A27 steel) tested in Hanford groundwater at 150°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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