IASCC INITIATION TEST OF NEUTRON IRRADIATED TYPE 316L STAINLESS STEEL IN SIMULATED BWR CONDITION TO EVALUATE THRESHOLD STRESS

von Chatani, K.
Veröffentlicht in International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (19. : 2019 : Boston, Mass.) 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors 2019 ; Volume 2 of 2 (2020)

FORMULATION OF THE IRRADIATION ASSISTED STRESS CORROSION CRACK GROWTH RATES FOR NEUTRON-IRRADIATED STAINLESS STEELS IN HIGH-TEMPERATURE WATER OF A BOILING WATER REACTOR

von Koshiishi, M.
Veröffentlicht in International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (19. : 2019 : Boston, Mass.) 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors 2019 ; Volume 1 of 2 (2020)