The neutronics studies of fusion fission hybrid power reactor
- School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi, 710049 (China)
In this paper, a series of neutronics analysis of hybrid power reactor is proposed. The ideas of loading different fuels in a modular-type fission blanket is analyzed, fitting different level of fusion developments, i.e., the current experimental power output, the level can be obtained in the coming future and the high-power fusion reactor like ITER. The energy multiplication of fission blankets and tritium breeding ratio are evaluated as the criterion of design. The analysis is implemented based on the D-type simplified model, aiming to find a feasible 1000MWe hybrid power reactor for 5 years' lifetime. Three patterns are analyzed: 1) for the low fusion power, the reprocessed fuel is chosen. The fuel with high plutonium content is loaded to achieve large energy multiplication. 2) For the middle fusion power, the spent fuel from PWRs can be used to realize about 30 times energy multiplication. 3) For the high fusion power, the natural uranium can be directly used and about 10 times energy multiplication can be achieved.
- OSTI ID:
- 22068952
- Journal Information:
- AIP Conference Proceedings, Vol. 1442, Issue 1; Conference: International conference on fusion for neutrons and subcritical nuclear fission, Varenna (Italy), 12-15 Sep 2011; Other Information: (c) 2012 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
BREEDING RATIO
DESIGN
HYBRID REACTORS
ITER TOKAMAK
NATURAL URANIUM
PLUTONIUM
PWR TYPE REACTORS
RADIOACTIVE WASTE PROCESSING
REACTOR FUELING
REPROCESSING
SPENT FUELS
TRITIUM RECOVERY