Service Properties of Reactor Structural Steels and Prediction of NPP Equipment Life With PWR-Type Reactors

In this paper the results obtained from the experimental investigation of Cr-Ni-Mo-V and Mn-Ni-Mo-V steel service properties used in the USSR reactor building, as well as the static crack resistance K{sub 1C} versus reference temperature dependence and Paris kinetic diagrams of fatigue crack growth rate in air and water of high parameters, are given.