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AbstractAbstract
[en] Microstructural observations are reported for a series of five commercial ferritic alloys, 2 1/4 Cr-1 Mo, H-11, EM-12, 416, and 430F, covering the composition range 2.25 to 17% chromium, following EBR-II irradiation over the temperature range 400 to 6500C and to a maximum fluence of 17.6 x 1022 n/cm2 (E > 0.1 MeV). These materials were confirmed to be low void swelling with maximum swelling of 0.63% measured in EM-12 following irradiation at 4000C to 14.0 x 1022 n/cm2. A wide range of precipitation response was found both as a function of alloy and irradiation temperature. Precipitates observed included M6C, Mo2C, Chi, Laves, M23C6, α' and a low temperature phase as yet unidentified. It is predicted, based on these results, that the major impact of irradiation on the ferritic alloy class will be changes in postirradiation mechanical properties due to precipitation
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Source
1981; 6 p; Fusion reactor materials meeting; Seattle, WA, USA; 9 - 12 Aug 1981; CONF-810831--45; Available from NTIS., PC A02/MF A01
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Report
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Conference
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