The in-reactor deformation of the PCA alloy

Abstract

This report documents the results from the irradiation of the PCA alloy in the Fast Flux Test Facility (FFTF). Both swelling and in-reactor creep data were obtained to a peak neutron dose corresponding to 80 dpa [ 16 × 10 22 n/cm 2 ( E > 0.1 MeV )]. These data are compared to the in-reactor deformation in cold worked 316 SS. The swelling data from this work for both PCA and 316 SS are also compared to swelling data on the 20% cold worked LSI alloy. This alloy is a titanium-stabilized austenitic steel developed for the liquid metal reactor program.