THE APPLICATION OF STRUCTURAL MATERIALS DATA FROM THE BN-350 FAST REACTOR TO LIFE EXTENSION OF LIGHT WATER REACTORS

摘要

This paper describes the results of investigations of 08Crl6NillMo3 (AISI 316 steel analogue) austenitic stainless steel irradiated in BN-350 breeder reactor at irradiation conditions close to that for Light Water Reactor (LWR) Internals. The pores were found in 08Crl6NillMo3 steel irradiated at temperature 280℃ up to rather low damage 1.3 dpa and with dose rate 3.9x10~(-9) dpa/s. There were obtained dose rate dependencies of yield strength, ultimate strength and ductility for 08Crl6NillMo3 steel irradiated up to 7-13 dpa at 302-311℃. These dependencies show a decrease in both yield strength and ultimate strength when dose rate decreases. There was observed an apparent decrease in total elongation when dose rate decreases, which was presumably connected with the pores formation in the steel at low dose rates.