STANDARD PRACTICE FOR CONDUCTING SURVEILLANCE TESTS FOR LIGHT-WATER COOLED NUCLEAR POWER REACTOR VESSELS, E 706 (IF) (E2-1985)
|Publication Date:||1 July 1982|
|ICS Code (Reactor engineering):||27.120.10|
This practice covers procedures for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in the beltline of light-water cooled nuclear power reactor vessels. This practice includes guidelines for designing a minimum surveillance program, selecting materials, and evaluating test results.
This practice was developed for all light-water cooled nuclear power reactor vessels for which the predicted maximum neutron fluence (E > 1 MeV) at the end of the design lifetime exceeds 1 X 1021 n/m2 (1 X 1017 n/cm2) at the inside surface of the reactor vessel.