Concept and nuclear performance of direct-enrichment fusion breeder blanket using UO2 powder.
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概要
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A new concept is presented for direct enrichment of fissile fuel in the blanket of a fusion-fission hybrid reactor. The enriched fuel produced by this means can be used in fission reactors without reprocessing. The outstanding feature of the concept is the powdered form in which UO<SUB>2</SUB> fuel is placed in the reactor blanket, where it is irradiated to the requisite enrichment for use as fuel in burner reactor, e.g. 3%. After removal from blanket, the powder is mixed to homogenize the enrichment. Fuel pellets and assemblies are then fabri-cated from the powder without reprocessing. The concept of irradiating UO<SUB>2</SUB> in powder eliminates the problems of spatial nonuniformity in fissile enrichment, and of radiation damage to fuel clad, encountered in attempting to enrich prefabricated fuel. Powder mixing for homogenization brings the additional benefit of removing volatile fission products. Also burnable poison can be added, as necessary, after irradiation.<BR>An extensive neutronic parameter survey showed that the optimum blanket arrangement for this enrichment concept is one presenting a fission suppressing configuration and with beryllium adopted as moderator. By this arrangement, the average <SUP>239</SUP>Pu enrichment obtained on the natural UO<SUB>2</SUB> fuel in the blanket reaches 3% after only 0.56 MW•yr/m<SUP>2</SUP> exposure. A conceptual design is presented of the blanket, together with associated fusion breeder, from which, practical application of the concept is shown to be promising.
- 一般社団法人 日本原子力学会の論文
著者
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Oka Yoshiaki
Nuclear Engineering Research Laboratory Graduate School Of Engineering The University Of Tokyo
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AN Shigehiro
Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo
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KASAHARA Takayasu
Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo
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