Tensile properties of the NLF reduced activation ferritic/martensitic steels after irradiation in a fast reactor spectrum to a maximum dose of 67 dpa

• Published in: Journal of nuclear materials Vol. 341; no. 2-3; pp. 141 - 147
• Main Authors: MALOY, Stuart A, JAMES, M. R, ROMERO, T. J, TOLOCZKO, M. B, KURTZ, R. J, KIMURA, A
• Format: Journal Article
• Language: English
• Published: Amsterdam Elsevier 15.05.2005
• Subjects: Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Fuels; Installations for energy generation and conversion: thermal and electrical energy; Nuclear fuels; Tokamak; Hardening; Nuclear fusion reactor; Martensitic steel; Fast reactor; Ferritic steel; Tensile property; Tension test; Strength; Nuclear reactor
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2005.01.013

The NLF series of steels are reduced activation ferritic-martensitic (RAFM) steels that are a part of the Japanese program to produce a suitable reduced activation ferritic-martensitic steel for the ITER project. Published reports on the NLF steels after about 35 dpa at 400 DGC by Kurishita et al., indicate that these steels have similar strength and better ductility than other RAFM steels such as the JLF steels and F82H irradiated at 400 DGC to similar doses. The tensile properties of NLF steels irradiated at ~400 DGC to doses as high as 67 dpa are presented here. Tensile tests were conducted at a strain rate of 5 x 10-4 s-1 at 25, 400 DGC, and 500 DGC. Variations in irradiation temperature in the range of 390-430 DGC had a relatively small, but definite effect on the tensile properties for tests conducted at 25, 400, and 500 DGC. The strongest hardening is observed for specimens irradiated at 390 DGC, and very little hardening is observed for specimens irradiated at 430 DGC. Strain rate jump tests were performed on NLF-0 and NLF-1 at 400 DGC after irradiation to 52 dpa. The rate sensitivity, m, is quite low, 0.003-0.005 and does not appear to be affected by irradiation at 52 dpa for an irradiation temperature of 430 DGC.