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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.
Yuuki Edao, Satoshi Fukada, Hidetaka Noguchi, Yasushi Maeda, Kazunari Katayama
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 831-835
Tritium Breeding | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST56-831
Articles are hosted by Taylor and Francis Online.
Rates and amounts of absorption and desorption of hydrogen and deuterium in a Li0.17Pb0.83 eutectic alloy are determined under the conditions of temperature of 400-700°C and the upstream H2 or D2 partial pressure of 103Pa-105 Pa by using a one-dimensional permeation pot. Because of small interaction between the alloy and dissolved atoms of hydrogen isotopes, the temperature dependence of the Sieverts' solubility constant for the Li0.17Pb0.83 -H or -D system, i.e., the enthalpy change of absorption or desorption, is small, and the absolute value of D solubility is higher than that of H. The isotope effect of diffusivity between H and D is very small. The generation rate and inventory of tritium (T) in a fusion blanket is estimated under an assumption of one-dimensional Li0.17Pb0.83 blanket system with a constant and uniform neutron flux.