US EPA

1442825 

Journal Article 

The Neutronics Studies of Fusion Fission Hybrid Power Reactor 

Zheng, Y; Wu, H; Zu, T; Yang, C; Cao, L 

2012 

Yes 

AIP Conference Proceedings
ISSN: 0094-243X
EISSN: 1551-7616 

AIP Conference Proceedings 

1442 

267-275 

10.1063/1.4706879 

WOS:000306895100032 

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. 

Fusion Fission Hybrid Reactor; Neutronics Analysis; Energy multiplication