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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.
T. A. Kenfield, W. K. Appleby, H. J. Busboom
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 347-352
Technical Paper | Material | doi.org/10.13182/NT77-A31948
Articles are hosted by Taylor and Francis Online.
Type 304 stainless steel has been irradiated to a fluence of 1.4 × 1027 n/m2, E > 0.1 MeV, in the solution-annealed and 10, 20, and 30% cold-worked conditions. Cold working does not impart a continuous reduction in swelling for this alloy. Indeed, in the temperature range from 475 to 550°C (748 to 823 K), the 10 and 20% cold-worked specimens showed more swelling than the alloy in the solution-annealed condition. This behavior appears to be a consequence of differing temperature dependences of swelling. Peak swelling in the cold-worked materials occurs somewhere between 475 and 550°C (748 and 823 K), while the solution-annealed condition peaks at a lower temperature.