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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.
Min-Jie Chuang, Shih-Jen Wang, Sheng-Yuan Fann, Show-Chyuan Chiang
Nuclear Technology | Volume 167 | Number 2 | August 2009 | Pages 247-253
Technical Paper | Fission Reactors | doi.org/10.13182/NT09-A8961
Articles are hosted by Taylor and Francis Online.
Generic severe accident guidelines (SAGs) of a boiling water reactor are developed based on the Mark-I containment system. There are many intrinsic features of Mark-III containment including the following: the drywell does not form a part of the primary containment boundary, it has large containment free volume, the drywell is enclosed by the primary containment, and the drywell and the primary containment are located parallel on the same elevation.Because of the features of the Mark-III system and its benefit to the containment flooding strategy, it is found that the associated containment flooding strategy can be simplified. The seven legs in the containment flooding strategy are reduced to four legs. The five rows of check logic are reduced to three. Simplifying the SAG charts whenever possible increases the probability of a successful outcome. The tedious and time-consuming work of identifying the reactor pressure vessel status can be removed. It saves time for decision making in emergency conditions.