NEUP CINR-19-16567: Irradiation-assisted Stress Corrosion Cracking of PWR-irradiated Type 347 Stainless Steel

This project will use material from commercial pressurized water reactor baffle-former bolts (neutron irradiated Type 347 steel), available from previous failure investigations and industry research, to conduct irradiation-assisted stress corrosion cracking initiation tests under controlled experimental conditions. The research will assess the dependence of this cracking phenomena on radiation damage and reactor water chemistry (potassium hydroxide versus lithium hydroxide).

Additional Info

Field	Value
Awarded Institution	Westinghouse Electric Company
PI	Mike Ickes