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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.
B. Habert, C. De Saint Jean, G. Noguere, L. Leal, Y. Rugama
Nuclear Science and Engineering | Volume 166 | Number 3 | November 2010 | Pages 276-287
Technical Paper | doi.org/10.13182/NSE09-85
Articles are hosted by Taylor and Francis Online.
An uncertainty propagation methodology relying on marginalization techniques was recently developed to produce covariance matrices between existing model parameters involved in describing neutron-induced reactions. This work has been implemented in the nuclear data assimilation tool CONRAD. The performance of the code was demonstrated through simplified test cases based on a Reich-Moore description of the 155Gd(n,) reaction. Results are compared with those produced via Monte Carlo techniques.