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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.
Eberhard Teuchert, Hans Joachim Rütten, Heinz Werner
Nuclear Technology | Volume 38 | Number 3 | May 1978 | Pages 374-383
Technical Paper | Fuel Cycle | doi.org/10.13182/NT78-A32035
Articles are hosted by Taylor and Francis Online.
For the pebble-bed high-temperature reactor, a wide choice is available for the design of the fuel elements and for the reactor fueling scheme. This flexibility has been utilized for the conception of different possibilities for the closure of the thorium fuel cycle. The easiest scheme is mixed-oxide recycling with repeated recycling of 236U. Loading recycle fuel into separate elements without thorium reduces the uranium ore demand by 13%. Entire separation of the feed and breed circuits brings another reduction of 5%. Furthermore, the feed-breed cycle allows the production of 233U for the near-breeder variant. This variant achieves a conversion ratio of 0.97, and it represents a possible choice for efficient protection of uranium ore resources. Within the span of uncertainties in the cost assumptions, fuel cycle costs are found to be comparable for all considered cycles, including the near-breeder.