Evaluation of IAEA Coordinated Program Steels and Welds for 288 C Radiation Embrittlement Resistance.

摘要

Eight steel materials supplied by the Federal Republic of Germany, France and Japan to the International Atomic Energy Agency (IAEA) Program on 'Analysis of the Behavior of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation' were irradiated at 288 C for assessments of relative notch ductility and dynamic fracture toughness change with approximately 2 x 10 to the 19th power n/cm squared, E > 1 MeV. Notch ductility and fracture toughness were determined, respectively, by Charpy-V and fatigue precracked Charpy-V test methods. An A533-B steel plate (HSST 03) produced in the USA was included in the irradiation test series for reference. The materials (plate, weld, forging) were found to be generally more resistant to radiation-induced embrittlement than the reference material. Observed dissimilarities in radiation sensitivity are attributed to copper content differences between the eight materials (0.01 to 0.07 percent copper range) and the reference plate (0.12 percent copper). Radiation resistances, however, correspond well with the trend of radiation resistance reported for USA-produced steels and welds having similar copper and phosphorus contents. A general correlation of transition temperature elevations measured independently by the Charpy-V and the precracked Charpy-V test methods was observed. (Author)