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Ductility Loss in Fast Reactor Irradiated Stainless Steel

A. L. Ward, J. J. Holmes

Nuclear Technology / Volume 9 / Number 5 / November 1970 / Pages 771-772

Note / Material / dx.doi.org/10.13182/NT70-A28755

Results from a postirradiation annealing study show that ductility losses in austenitic stainless steels result from a combination of helium embrittlement and displacement damage at temperatures above Tm/2. Residual losses following removal of the displacement damage by annealing at ∼0.8 Tm are attributed to helium embrittlement alone.