Irradiation hardening and loss of ductility of type 316L(N) stainless steel plate material due to neutron-irradiation
- Netherlands Energy Research Foundation, Petten (Netherlands)
Type 316 stainless steel is the primary candidate austenitic structural material for fusion first wall constructions. Here, type 316L(N) stainless steel plate material has been irradiated up to 10 dpa at temperatures of 80, 225, 325, and 425 C in the High Flux Reactor (HFR) of Petten. Tensile tests have been performed in the temperature range from RT to 575 C at a conventional strain rate of 5 {times} 10{sup {minus}4} s{sup {minus}1}. The results of the tensile tests are analyzed in terms of irradiation hardening and loss of ductility due to irradiation. Tensile properties saturate in the early stage (within 0.65 dpa) at the lowest applied irradiation temperature. It is indicated that the most severe degradation of tensile ductility occurs in the temperature range of 275 to 350 C. Comparison with literature data revealed a large scatter in irradiation hardening at irradiation temperatures above 325 C.
- OSTI ID:
- 524839
- Report Number(s):
- CONF-940657--
- Country of Publication:
- United States
- Language:
- English
Similar Records
Comparison of the irradiated tensile properties of a high-manganese austenitic steel and type 16 stainless steel
Mechanical Properties of Additively Manufactured 316L Stainless Steel Before and After Neutron Irradiation–FY23