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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.
Karol J. Mysels
Nuclear Technology | Volume 44 | Number 2 | July 1979 | Pages 203-209
Technical Paper | Reactor | doi.org/10.13182/NT79-A32255
Articles are hosted by Taylor and Francis Online.
In a high-temperature gas-cooled reactor, there is a narrow gap between the fuel stick and the graphite septum separating it from the rapidly flowing helium coolant. Porosity of the graphite permits a small part of the helium to flow through the gap. This parasitic “transverse flow” may be significant in fission product transport. The extent and pattern of this flow is calculated in terms of the resistivities to gas flow: axially for the gap and radially for the septum. The latter was measured for a number of Fort St. Vrain elements, and the former was obtained from specifications. The calculated flow in a fuel hole amounts to a fraction of 1 cm3/s on the average and may reach slightly over 1 cm3/s.