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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. N. Chung, P. S. Ayyaswamy
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 603-610
Technical Paper | Reactor | doi.org/10.13182/NT77-A31869
Articles are hosted by Taylor and Francis Online.
Heat removal rates from containment spray droplets following a loss-of-coolant accident in a nuclear reactor have been calculated by three different droplet models: the complete mixing model, the model with internal circulation, and the rigid sphere. Irrespective of the model, the thermalization time is found to increase with increasing droplet size. It is noticed that the thermalization times predicted by the complete mixing and nonmixing models either underestimate or overestimate the value provided by the internal circulation model. It is concluded that the effect of internal circulation cannot be ignored in estimating heat removal rates from spray droplets.