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A subcritical, helium-cooled fast reactor for the transmutation of spent nuclear fuel

机译:次临界氦冷却快堆用于乏燃料的the变

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A design concept and supporting analysis are presented for a He-cooled fast reactor for the transmutation of spent nuclear fuel. Coated transuranic (TRU)fuel particles in a SiC matrix are used. The reactor operates subcritical (k <= 0.95), with a tokamak D-T fusion neutron source, to achieve > 90% TRU burnup in repeated five-batch fuel cycles, fissions 1.1 tonnes/full-power year, and produces 700 MW(electric) net electrical power. The reactor design is based on nuclear, fuels, materials, and separations technologies being developed in the Generation-IV, Next Generation Nuclear Plant, and Advanced Fuel Cycle Initiative programs and similar international programs, and the fusion neutron source is based on the physics and technology supporting the ITER design.
机译:介绍了一种用于乏核燃料trans变的氦冷快堆的设计概念和支持分析。使用SiC基体中的涂层超铀(TRU)燃料颗粒。该反应堆使用托卡马克DT聚变中子源运行于亚临界状态(k <= 0.95),可在重复的五批燃料循环,裂变1.1吨/全功率年中实现> 90%的TRU燃耗,并产生700兆瓦(电)净电力。反应堆设计基于第四代,下一代核电站和先进燃料循环倡议计划以及类似的国际计划中正在开发的核,燃料,材料和分离技术,而聚变中子源则基于物理学和支持ITER设计的技术。

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