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자료유형
학술저널
저자정보
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제50권 제7호
발행연도
2018.1
수록면
1,060 - 1,067 (8page)

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A feasibility of reusing option of spent nuclear fuel in a fusion-fission hybrid system without partitioningwas checked as an alternative option of pyro-processing with critical reactor system. Neutronic studywas performed with MCNP 6.1 for this option, direct reuse of spent PWR fuel (DRUP). Various optionswith DRUP fuel were compared with the reference design concept; transmutation purpose blanket with(U-TRU)Zr fuel loading connected with pyro-processing. Performance parameters to be compared are transmutation performance of transuranic (TRU) nuclides,required fusion power and tritium breeding ratio (TBR). When blanket part is loaded only withDRUP, initial keff level becomes too low to maintain a practical subcritical system, increasing the requiredfusion power. In this case, production rate of TRU nuclides exceeds the incineration rate. Design optimization is done for combining DRUP fuel with (U-TRU)Zr fuel. Reactivity swing is reducedto about 2447 pcm through fissile breeding compared to (U-TRU)Zr fuel option. Therefore, a requiredfusion power is reduced and tritium breeding performance is improved. However, transmutation performancewith TRU nuclides especially 241Am is degraded because of softening effect of spectrum. It isknown that partitioning and transmutation should be accompanied with fusion-fission hybrid system forthe effective transmutation of TRU.

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