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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.
Kashuai Du, Po Hu, Lefu Zhang, Weibo Wang
Nuclear Science and Engineering | Volume 193 | Number 10 | October 2019 | Pages 1129-1146
Technical Paper | doi.org/10.1080/00295639.2019.1591094
Articles are hosted by Taylor and Francis Online.
In the passive containment cooling system (PCCS) of an AP1000-type pressurized water reactor nuclear power plant, the air convective heat transfer in the external channel of the containment plays a key role under accident conditions. In this study, the containment external channel is simplified into a large-scale rectangular channel with asymmetric heating, and an experimental and numerical study is conducted to evaluate the air heat transfer characteristics. In addition, the effect of the entry form, which comprises an irregular inlet duct and a pore plate, is considered. First, the results show that heat transfer is enhanced by the entry form, which can be verified by numerical simulation and experiment. Second, when analyzing the air heat transfer characteristics of the actual PCCS annular channel, the Gnielinski correlation is relatively conservative since this correlation hugely underestimates the heat transfer rate of numerical cases in a large-scale rectangular channel with the entry form.