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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.
Eugene Normand
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 65-73
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31959
Articles are hosted by Taylor and Francis Online.
The effect of halogen plateout sources on containment post-loss-of-coolant accident dose rates has been evaluated. The main approach utilized has been to compare the dose rates due to halogen plateout and halogen immersion (or atmospheric) sources, assuming each is comprised of an equal inventory of radioiodines. Based on the parameters chosen, including the use of only the primary 131I photon, 0.36 MeV, for all calculations, the gamma-ray dose rate from the atmospheric component will always dominate over the plateout component for full containment configurations. However, for small chambers within the containment, the atmospheric and plateout dose rates are relatively comparable, so that determining which is greater depends on the location of the dose point.