Tritium Self-Sufficiency and Neutron Shielding Performance of Self-Cooled Liquid Blanket System for Helical Reactor
作者： Teruya Tanaka , Takeo Muroga , Akio Sagara
DOI: 10.13182/FST05-A738
关键词:
摘要: Compatibility between tritium self-sufficiency and neutron shielding performance of self-cooled liquid blanket systems without solid multiplier was investigated for the purpose application to conceptual helical reactor design modified FFHR2 having space 120 cm. The results neutronics calculation indicated that all Li/V-alloy, Flibe/V-alloy Flibe/JLF-1 (Reduced Activation Ferritic steel) blankets are feasible breeding ability performance. With use vanadium alloys, operation efficiency will be enhanced.
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