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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.
A. Gruel, P. Leconte, D. Bernard, P. Archier, G. Noguère
Nuclear Science and Engineering | Volume 169 | Number 3 | November 2011 | Pages 229-244
Technical Paper | doi.org/10.13182/NSE10-113
Articles are hosted by Taylor and Francis Online.
To take into account the reactivity loss in spent fuels, an experimental program was set up in 1993 at CEA-Cadarache, France, oscillating separated fission products (FPs) in the MINERVE reactor. Reactivity worth measurements of small samples allow the extraction of information about nuclear data of the studied isotopes. A fully validated calculation scheme has been implemented to interpret pile-oscillation measurements. Therefore, calculation over experiment ratios can be accurately transposed to trends in the integral capture cross section of the FPs. With the European JEFF3.1.1 library, results show a discrepancy below 3% for several nuclides: 155Gd, 149, 152Sm, 143Nd, and 95Mo, but improvements may be needed for some others: 133Cs, 103Rh, 99Ru, and 153Eu. Based on the Integral Data Assimilation technique, we propose new thermal cross-section values, (348 ± 14) b and (42 478 ± 1793) b, for two of the most absorbing nuclides, 143Nd and 149Sm, respectively.