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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.
J. B. Sun, H. D. Warren
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 249-261
Technical Paper | Reactor | doi.org/10.13182/NT77-A31939
Articles are hosted by Taylor and Francis Online.
To determine the accuracy of the neutron transport computer code used to predict 16N production rates, data on 16O(n, p)16N reaction rates were obtained by performing an 16O activation experiment. Measured absolute 16N production rates are compared to the calculated data. The comparison indicates that calculations using ENDF/B-II data consistently overestimate 16N production rates by a factor that ranges from 1.06 to 2.00. Good agreement between measurements and ENDF/B-IV calculations reveals that the latest version of the nuclear data used in the code is remarkably improved over previous versions.