The objective of this research is to determine the effects of radiation-induced displacement damage on the corrosion of 316L stainless steel in high temperature water. The benchmark experimental approach was to transmit 5.4 MeV protons through 316L stainless steel and into an autoclave containing 320 °C water. The displacement damage rate is set to a nominal 7 × 10–7 dpa/s, and the resulting radiolysis-inducing dose rate is 650–700 kGy/s. To separate the effects of water radiolysis from displacement damage, a specialized sample geometry and steam environment were employed. 316L stainless steel bars were placed in the autoclave with a face parallel to the proton beam to receive exposure to similar levels of water radiolysis with negligible d...