PREDICTION OF DUCTILE FRACTURE TOUGHNESS FOR NEUTRON-IRRADIATED REACTOR PRESSURE-VESSEL STEELS. PART 2

摘要

The influence of neutron irradiation on the critical strain in tensile testing of smooth cylindrical specimens and on the local critical strain in ductile fracture of cracked specimens is simulated for 15Kh2MFA reactor pressure-vessel steel. Based on a series of calculations, we have developed an engineering scheme for estimating the irradiation-induced decrease in the upper-shelf level of the K_(Ic)(T) function.