Evaluation of ferritic alloy Fe-2-1/4Cr-1Mo after neutron irradiation - microstructure development [report]

D.S. Gelles
1984 unpublished
COPYRIGHT LICENSE NOTICE ., r ' this irticle, the Publishet ind/or recipient acknowledges the U.S. nnPllMf NT Gowtnmeflt's rifht to teliin a none>clu»ve, royaltj-fiee hcense in and to an; copjtniM niBinmH Of "^^ Uutun<>-" .AO^ SUMMARY Microstructural examinations are reported for nine specimen conditions of 2-l/4Cr-lMo steel which had been irradiated by fast neutrons over the temperature range 390 to 5ICC. Two heats of material were involved, each with a different preirradiation heat treatment,
more » ... ion heat treatment, one irradiated to a peak flunce of 5.1 x 10^^ n/cm^ (E >0.1 MeV) or 24 dpa and the other to 2.4 x 10^ 2 n/cm (E >0.1 MeV) or 116 dpa. Void swelling is found following irradiation at 400°C in both conditions and to 480°C in the higher fluence conditions. Concurrently dislocation structure and precipitation formed. Peak void swelling, void density, dislocation density and precipitate number density developed at the lowest temperature, 'v400°C, whereas mean void size, and mean precipitate size increased with increasing irradiation temperature. The examination results are used to provide interpretation of in-reactor creep, density change and post irradiation tensile behavior.
doi:10.2172/7120109 fatcat:eemzn3q5lfcwrp4e6n3bkmx52q