TENSILE PROPERTIES OF TYPE-316 STAINLESS-STEEL IRRADIATED IN A SIMULATED FUSION-REACTOR ENVIRONMENT

Tensile and fracture properties of type 316 stainless steel in the annealed and 20% coldworked conditions were investigated to neutron fluences producing 16 dpa and 1000 at. ppm He resulting from irradiation in the High Flux Isotope Reactor. Tensile elongations remained above 6% at 350 and 450°C and 4% at 575°C. Fracture behavior has been examined in the 20% cold-worked material. At 350°C the fracture mode is unchanged by irradiation and is characterized by ductile tearing. At 450°C irradiation causes the fracture mode to change from ductile tearing to crystallographic fracture which may occur along the slip bands introduced by the cold working. At 575°C the fracture is changed from ductile transgranular to intergranular. The tensile properties observed are believed to be adequate for fusion reactor service within the values of damage parameters investigated. © 1979.