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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.
Robert E. Rothe, Inki Oh
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 207-225
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Fuel Cycle | doi.org/10.13182/NT78-A32106
Articles are hosted by Taylor and Francis Online.
Seventy-six benchmark critical conditions are reported. Both material and geometry properties are so well determined as to reduce greatly any contribution to a theoretical/experimental discrepancy attributable to the experiment. The program uses uranyl nitrate solution with the uranium enriched to 93.17% 235U. The concentration ranges from 54.89 to 369.96 g U/ℓ Unreflected experiments are reported, as well as measurements within thick-walled cubical reflector shells composed of such common materials as concrete and plastic. For experiments using a single tank, the diameter of the tank ranged from 27.88 to 50.69 cm, and arrays of up to 16 cylinders have containers of two diameters: 16.12 and 21.12 cm. Containers composed of aluminum or stainless steel are studied. For all these parameters, the critical heights range from 17.13 to 110.20 cm.