Inconel 600 was irradiated in HFIR to provide a partial simulation of fusion reactor service. Samples were irradiated at 55 to 700/sup 0/C, to investigate swelling and postirradiation tensile properties as a function of irradiation and test temperatures under conditions of concurrent displacement damage and helium production. Helium contents from 600 to 1800 appm and displacement levels of 4 to 9 dpa were achieved, and the results are used to estimate performance in a fusion reactor environment. Tensile property measurements and fractography on the same samples showed strength values increased for irradiation at 55 to 400/sup 0/C but decreased below …
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Inconel 600 was irradiated in HFIR to provide a partial simulation of fusion reactor service. Samples were irradiated at 55 to 700/sup 0/C, to investigate swelling and postirradiation tensile properties as a function of irradiation and test temperatures under conditions of concurrent displacement damage and helium production. Helium contents from 600 to 1800 appm and displacement levels of 4 to 9 dpa were achieved, and the results are used to estimate performance in a fusion reactor environment. Tensile property measurements and fractography on the same samples showed strength values increased for irradiation at 55 to 400/sup 0/C but decreased below unirradiated values for irradiations at 600 and 700/sup 0/C.
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