Literature survey of radiation damage on type 304 and 316 stainless steels; Tensile and fatigue properties

not registered; not registered; Shibahara, Itaru*; not registered

In the case of prototype fast reactor "MONJU", neutron shieldings are supposed to put at the lower part of each subassembly to reduce the neutron fluence at the coresupport plate to 310 n/cm (0.1 MeV). Types 304 or 316 stainless steel will be used as the core support, so radiation effects on tensile and fatigue properties of these materials were surveyed and compiled. The results obtained are summarized as follows. (1)If the mechanical property required at the end of reactor lifetime is assumed to be ruptured elongation after tensile test of 10%, objective design fluence limit of 310 n/cm (0.1 MeV) may be adequate for type 304 stainless steel. (2)On the same assumption, fluence limit for type 316 stainless steel is about as twice as that for type 304 stainless steel. (3)As the fatigue data on irradiated materials are extremely limited, it is impossible to make clear the effect of fluence on fatigue properties. However, it is supposed that the radiation effect on fatigue properties at 400C 550C is not so dominant at the fluence below 210n/cm (0.1 MeV). In addition, this report can be widely used as a document, which compiles tensile and fatigue data on irradiated types 304 and 316 stainless steels.