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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.
R. A. Renzetti, H. R. Z. Sandim, A. F. Padilha, D. Raabe, R. Lindau, A. Möslang
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 22-26
doi.org/10.13182/FST11-A12400
Articles are hosted by Taylor and Francis Online.
Oxide dispersion strengthened (ODS) ferritic/martensitic (FM) steels are promising candidates for structural applications in future fusion power reactors. In order to evaluate the thermal stability of 80% cold-rolled ODS-EUROFER, samples were annealed for 1 h at temperatures up to about 0.9 Tm, where Tm is the absolute melting point. The characterization of the annealed samples was performed using transmission electron microscopy and electron backscatter diffraction. Results show that static recovery is the main softening mechanism of this steel when annealed below 800°C. The volume fraction of recrystallized grains is quite small (below 0.10). Above 900°C, martensitic transformation takes place causing pronounced hardening. Large M23C6 particles are found at the grain boundaries after tempering at 750°C for 2 h.