Prediction of crack growth resistance for ductile fracture of neutron-irradiated reactor pressure-vessel steels. Part 2

摘要

Modeling of the effect of neutron irradiation on the critical strain in tensile testing of smooth cylindrical specimens and on local critical strain in ductile fracture of specimens with cracks was performed as applied to a 15Kh2MFA reactor pressure-vessel steel. On the basis of a number of numerical investigations performed an engineering scheme for estimating a decrease in the upper-shelf level of the K{sub}(Ic)(T) relation in the process of irradiation was developed.