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Fracture Resistance of HT-9 After Irradiation at Elevated Temperature

Hawthorne, JR.V. ProvenzanoFA. Smidt

出版	ASTM International, 1981
URL	http://books.google.com.hk/books?id=btR2zgEACAAJ&hl=&source=gbs_api

註釋

HT-9, a 12 percent chromium martensitic stainless steel of interest for use in ducts for fast reactors and as a first-wall material in magnetic fusion reactors, was irradiated in the experimental breeder reactor II to obtain the first evaluation of fracture toughness changes produced by high-temperature/high-fluence irradiation in this class of alloy.