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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.
I. Alekseev, O. Fedorchenko, P. Kravtsov, A. Vasilyev, M. Vznuzdaev
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 407-410
Technical Paper | Isotope Separation | doi.org/10.13182/FST08-A1841
Articles are hosted by Taylor and Francis Online.
The Deuterium Removal Unit (DRU) has been designed and built at the Petersburg Nuclear Physics Institute (PNPI) to produce isotopically pure hydrogen with deuterium content less than 1 ppm. The cryogenic distillation column of 2.2 cm inner diameter and 155 cm packing height is the main element of the DRU. Column performances at different hydrogen distillation operating modes have been measured. The height equivalent to theoretical plate (HETP) for the column is 2.2 cm and almost constant over a wide range of vapour flow rates. Deuterium depleted hydrogen with a deuterium content of less than 0.1 ppm was produced in required quantity.