A face centered cubic chromium-based material has been observed to resist stress corrosion cracking in simulated reactor water, even in the cold worked, high strength condition. Strength levels up to 1100 MPa have been investigated in both PWR and BWR simulated reactor coolant. While all common nuclear structural materials have exhibited stress corrosion cracking in one or both of these environments, the new material remained free from stress corrosion crack growth. Testing was done with precracked fracture mechanics specimens. Keywords: Stress corrosion cracking, chromium based material, alloy 33, high strength.