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Rikizo Watanabe
Nuclear Technology | Volume 66 | Number 1 | July 1984 | Pages 69-74
A. Selection, Production, and Development of Alloys for HTGR Component | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33456
Articles are hosted by Taylor and Francis Online.
A grain boundary precipitation treatment was studied for the purpose of improving the high-temper-ature low-cycle fatigue strength of a Ni-23% Cr- 18% W alloy, SSS113M, which had been developed as an intermediate heat exchanger material of very high temperature reactors and evaluated as the best alloy in the national R&D program of nuclear steelmaking in Japan. A conventional standard solution treatment of 1300°C × 1 h water quenched does not cause any grain boundary precipitation in SSS113M, but an additional heat treatment of 1250°C × 1 h causes discontinuous grain boundary precipitation of the alpha-tungsten phase. This grain boundary precipitation treatment results in two- to fivefold increases of low-cycle fatigue lives at 800°C as well as slight increases of the creep and stress rupture strength at 1000°C.