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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.
M. G. Chasanov, W. H. Gunther, L. Baker, Jr.
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 120-128
Radiation Environments in Nuclear Reactor Power Plant | Fuel | doi.org/10.13182/NT77-A31965
Articles are hosted by Taylor and Francis Online.
The capability for removal of heat from a pool of molten fuel under postaccident conditions is an important consideration in liquid-metal fast breeder reactor safety analysis. No experimental data for pool heat transfer from molten UO2 under conditions simulating internal heat generation by fission product decay have been reported previously in the literature. An apparatus to provide such data was developed and used to investigate heat transfer from pools containing up to 7.5 kg of UO2; the internal heat generation rates and pool depths attained cover most of the ranges of interest for postaccident heat removal analysis. It was also observed in these studies that the presence of simulated fission products corresponding to ∼150 000 kW-day/kg burnup had no significant effect on the observed heat transfer.