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The Neutronics Studies of Fusion Fission Hybrid Power Reactor

The Neutronics Studies of Fusion Fission Hybrid Power Reactor. Youqi Zheng Ph. D N uclear E ngineering C omputational P hysics Lab. Xi’an Jiaotong University. Contents. Background Fusion Source and Blanket Design Neutronics Design and Sensitivity Analysis Conclusions.

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The Neutronics Studies of Fusion Fission Hybrid Power Reactor

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  1. The Neutronics Studies of Fusion Fission Hybrid Power Reactor Youqi Zheng Ph. D Nuclear Engineering Computational Physics Lab. Xi’an Jiaotong University

  2. Contents • Background • Fusion Source and Blanket Design • Neutronics Design and Sensitivity Analysis • Conclusions

  3. Background(1/3) A long way for the pure fusion energy, but A short way for the application of fusion source It is well recognized that the fusion fission hybrid power reactor is an important early use of fusion source 2050 2030 2018 NOW 3

  4. Background(2/3) After 2000 R&D of Transmutation 1991-2000 R&D of Fuel Breeding 1986-1990 R&D of Reactor Concept 1980-1985 Idea Proposal R&D of hybrid reactor in China R&D of Hybrid Power Reactor (National Magnetic Confinement Fusion Science Program, 2010) Re-evaluation for Producing Energy, Breeding and Transmutation 4

  5. Background(3/3) • The target—A hybrid power reactor • 1000MWe Power Output for 5 years • Tritium self-sustaining considering 5% loss • Applying the existing fission technology as much as possible • Sufficient energy multiplication of blanket for different fusion power • The first step • Determining the outline of reactor • Determining the candidate fuel • Evaluating the feasibility

  6. Contents • Background • Fusion Source and Blanket Design • Neutronics Design and Sensitivity Analysis • Conclusions

  7. Fusion Source and Blanket Design (1/4) • The referred fusion reactor • Citing from the works on FDS-I by ASIPP (under the cooperation in National Magnetic Confinement Fusion Science Program )

  8. Fusion Source and Blanket Design (2/4) • Preliminary evaluation of water cooling blanket For the fuel pins and pressurized water coolant with 15.5MPa 200mm is required for the FW based on the press analysis (Referring: for a PWR vessel 43mm is required , but the practical one is >200mm)

  9. Fusion Source and Blanket Design (3/4) • The modular-type pressure tube blanket

  10. Fusion Source and Blanket Design (4/4) • The simplified evaluation model

  11. Contents • Background • Fusion Source and Blanket Design • Neutronics Design and Sensitivity Analysis • Conclusions

  12. Neutronics Design and Sensitivity Analysis (1/4) • Energy multiplication requirements of the fission blanket For the 50MW fusion power Keff >0.9 For the 100~200MW fusion power Keff~0.8 For the 500MW fusion power Keff~0.6

  13. Neutronics Design and Sensitivity Analysis (2/4) • Keff varying in the lifetime of different fuels Reprocessed fuel for high energy multiplication Spent fuel for middle energy multiplication Natural uranium fuel for low energy multiplication

  14. Neutronics Design and Sensitivity Analysis (3/4) • High energy multiplication blanket Burnable poison is another choice 4.5%w/o Pu More plutonium content Flattened burn-up process 14.3%w/o Pu Moderator-fuel ratio 1.0 Gd2O3 0.85%w/o

  15. Neutronics Design and Sensitivity Analysis (4/4) • Low energy multiplication blanket • Higher fusion power and released blanket performance Moderator-fuel ratio 0.5 Modified blanket Moderator-fuel ratio 1.0 The same blanket

  16. Contents • Background • Fusion Source and Blanket Design • Neutronics Design and Sensitivity Analysis • Conclusions

  17. Conclusions (1/2) • The reprocessed fuel containing existing plutonium from PWRs makes the hybrid power reactor feasible in the coming future • Progress of fusion technology may encourage the more easier fuels like the natural uranium fuel and directly burning the spent fuel from PWRs • Advanced work can and should be boosted based on the analysis

  18. Conclusions (2/2) • Discussions • High energy multiplication • Fuel support of the reactors • ~40tons plutonium will be loaded every 5 years • Control of the reactors • 90 times multiplication down to 60 times • Low energy multiplication • For the natural uranium fuel, the required small moderator-fuel ratio is very difficult to achieve for the pressure tubes • For the spent fuel, the fuel processing before loading

  19. eutronics valuation omprehensive ackage ovelty ndeavor ooperation ersist Thank you ! Welcome to: http://necp.xjtu.edu.cn

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