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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.
A. Razani, S. Yee, M. Nagel
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 264-274
Technical Paper | Fuel | doi.org/10.13182/NT77-A31788
Articles are hosted by Taylor and Francis Online.
For the design of control elements for a gas-cooled fast breeder reactor, accurate heat generation rates in the element must be known. The nuclear heating rates in all sections of the control element and the contribution of all radiation sources to the distribution of nuclear heating in the element are evaluated. The emphasis is placed on the direct neutron heating of the B4C control rod and on gamma-ray transport and energy deposition in the stainless-steel cladding and guide tube. The calculations include the helium and tritium production within the B4C control rod.