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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
D. T. Raske, C. F. Cheng
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 101-110
Technical Paper | Material | doi.org/10.13182/NT77-A31834
Articles are hosted by Taylor and Francis Online.
The fatigue crack-growth behavior of Type 304 stainless-steel base metal and Type 308 stainless-steel weld metal at elevated temperature was investigated using axially loaded single-edge-notch specimens. The crack-growth rates were determined and are presented as a function of the stress-intensity factor range. Both the base- and weld-metal specimens were tested in the as-received (or as-welded) and thermally aged condition. The results indicate that the crack-growth rates in the weld metal are significantly lower than in the base metal. In addition, aging at 593°C for 1000 h improved the resistance to fatigue crack growth in both the base and weld metals.