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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.
Yeon Soo Kim, Gerard L. Hofman, James L. Snelgrove
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 18-24
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3686
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Fission gas release and fuel expansion of irradiated uranium-zirconium hydride fuel were measured during fuel heating to melting. The first indication of melting occurred at approximately the uranium-cladding eutectic temperature, whereas complete melting took place at the U metal melting point. Fission gas release began with the onset of uranium-cladding melting and gradually increased with rising temperature. Two sharp peaks in the fission gas release were observed corresponding to the events of uranium-zirconium eutectic melting and uranium melting. The fractional release was much higher than that measured previously for fuel without cladding at comparable temperatures.