Standard Recommended Practice for SURVEILLANCE TESTS FOR NUCLEAR REACTOR VESSELS
|Publication Date:||1 March 1973|
|ICS Code (Reactor engineering):||27.120.10|
This recommended practice covers procedures for irradiating and testing mechanical test specimens for the purpose of monitoring and evaluating. at periodic intervals. the radiation-induced changes occurring in the mechanical properties of the reactor vessel steels of light water-cooled nuclear power reactors.
Surveillance tests are divided according to application into two cases:
Cast A-Where both the predicted increase in transition temperature of the reactor vessel steel is 100 F (37.8 C) or less and the calculated peak neutron fluence (E > I MeV) of the reactor vessel is 5 x 1018 n/cm2 or less.
Case B-Where the predicted increase in transition temperature of the reactor vessel steel is greater than 100 F (37.8 C) or where the calculated peak neutron fluence (E > I MeV) of the reactor vessel is greater than 5 x 1018 n/cm2