Fusion-Fission Hybrid Nuclear Reactors: For enhanced nuclear fuel utilization and radioactive waste reduction

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Nuclear energy is contributing to the long-term solution to stave off climate change. However, current nuclear fission technology accesses only about 1-3% of the nuclear energy content of natural uranium, which is inefficient, and also creates a radioactive waste disposal problem.

Combining nuclear fission technology with emerging nuclear fusion technology to create a fusion-fission hybrid would yield extra fusion neutrons to 1) convert much more of the uranium into fissionable material, which would increase efficient utilization of the nuclear fuel resource, and 2) significantly reduce (by fission) the most long-lived radioactive nuclear waste.

This book describes fusion-fission hybrid physics and technology. The first parts briefly review nuclear fission principles and describe design and safety of nuclear fission reactors; then the fundamentals of nuclear fusion and fusion reactor concepts are described, together with ongoing and future challenges and anticipated developments in this not-yet matured technology. Chapters cover the scientific basis of nuclear fission and the fission fuel cycle, advanced fission reactors, safety aspects, the scientific and technological basis of nuclear fusion power, future improvements expected, and then the fusion-fission hybrid (FFH) breeder and burner reactor concept principles, with illustrative FFH design concepts, safety analyses, and examples of the use of fusion neutrons for helping to achieve burning and breeding fission fuel cycles.

This concise work is essential reading for researchers and policy makers in nuclear energy research and engineering, including advanced students.

Author(s): Weston M. Stacey
Series: IET Energy Engineering Series, 225
Publisher: The Institution of Engineering and Technology
Year: 2022

Language: English
Pages: 296
City: London

Cover
Contents
List of figures
List of tables
About the author
Acknowledgments
Preface
1 Introduction
2 Nuclear electric power production
3 Scientific basis of nuclear fission energy
4 Uranium nuclear fission power fuel cycle
5 Fission energy fuel resources
5.1 Uranium resources
5.2 Thorium resources
6 Technological basis of nuclear fission power
7 Conversion of nuclear fission energy to electrical energy
8 Advanced fission reactors
9 The Nuclear Reactor Physics, Nuclear Reactor Engineering, Plasma Physics, and Fusion Technology disciplines
10 Safety of nuclear fission power reactors
11 The nuclear fission power fuel cycle
12 Scientific and technological basis of nuclear fusion power
13 Nuclear fusion power reactor studies
14 Future improvements in fusion physics and technology
15 Fusion–fission hybrid reactors
16 Principles and technical rationale of the fusion–fission hybrid breeder and burner reactors
17 Illustrative future fusion–fission hybrid reactor designs
17.1 SABR#1 Na loop-cooled tokamak FFH design with ANL fuel
17.2 SABR#1 Na loop-cooled tokamak with European fuel type
17.2.1 SABR#1 fuel shuffling
17.3 SABR#2 design
17.4 SABR#3 design
17.4.1 Thermal property data and empirical correlations
17.4.2 Design basis accidents
17.5 Tandem mirror FFH designs
17.6 Mirror designs discussion
17.7 Summary of the mirror FFH
18 SABR tokamak burner fuel cycles (using fusion neutrons to fission nuclear waste and close the back end of the fission fuel cycle
19 Computational models for tritium breeding ratio and fissile breeding ratios
19.1 Design constraints
19.2 Results and discussion
19.2.1 TBR case
19.2.2 FBR case
19.2.3 Neutronic effect of insulating sheath
19.2.4 Neutron spectra comparison
19.2.5 Power distributions
19.2.6 Comparison of SABrR to critical fast reactor system
19.3 Conclusion
20 Physics and engineering design constraints on fusion–fission hybrids
20.1 Input electrical power requirement
20.2 Comparison of waste thermal energy
20.2.1 Comparison of plant electrical energy gain
20.2.2 Limitations on fusion neutron source capabilities for transmutation reactors
20.2.3 Radiation damage limits to the first wall
20.2.4 Thermal limits to the first wall
20.2.5 Tokamak physics limits
20.2.6 Engineering limits on a tokamak fusion neutron source
21 Status of fusion development vis-à-vis a neutron source for FFH
22 Fusion neutron enhancement of a breeding nuclear fission fuel cycle
22.1 Closing the fission fuel cycle with a burner FFH
23 Using fusion neutrons to achieve a burning fission fuel cycle
23.1 Introduction
23.2 The SABR tokamak FFH design concept
23.2.1 Overview
23.2.2 Fuel element and fuel assembly design
23.2.3 SABR fuel assemblies for European MA-rich fuel
23.2.4 Fusion neutron source
23.2.5 SABR fuel cycle
23.2.6 SABR fuel cycle simulations
23.2.7 Accumulated radiation damage versus burnup for metal-TRU fuel
23.2.8 Minor actinide burner
23.3 Conclusions
24 Fuel cycle methodology, summary and conclusions
24.1 Calculation methodology
24.1.1 Design constraints
24.2 Results and discussion
24.2.1 TBR case
24.2.2 FBR case
24.2.3 Neutronic effect of insulating sheath
24.2.4 Neutron spectra comparison
24.2.5 Power distributions
24.2.6 Comparison to critical fast reactor system
24.3 Conclusion
25 Using fusion neutrons to achieve a breeding fission fuel cycle
25.1 Introduction
25.2 SABrR design concept
25.2.1 Fusion neutron source
25.2.2 Annular fast reactor
25.3 Computational model
25.3.1 Design constraints
25.4 Results and discussion
25.4.1 FBR case
25.5 Neutronic effect of insulating sheath
25.5.1 Neutron spectra comparison
25.5.2 Power distributions
25.5.3 Comparison with critical fast reactor system
26 Dynamic safety analyses of FFH reactors
26.1 Sodium loop-cooled fast reactor (SABR#1)
26.2 Introduction (SABR#1)
26.3 SABR#1 design overview
26.4 Dynamics calculation model
26.5 Accident simulations
26.5.1 Loss-of-flow accident
26.5.2 Loss-of-heat-sink accident
26.5.3 Loss-of-power accident
26.5.4 Worst possible control rod accident
26.5.5 Control rod ejection
26.5.6 Accidental increase in fusion neutron source strength
26.6 Summary and conclusions for “point kinetics” analyses
26.7 Nodal dynamics model
26.7.1 Neutron kinetics model
26.7.2 Calculation of nodal kinetics terms
26.7.3 Calculation of feedback effects
26.7.4 Thermal-hydraulic model
26.7.5 Modeling the coupled cores
26.7.6 Modeling the heat exchanger
26.7.7 Modeling the sodium pools
26.7.8 Thermal property data and empirical correlations
26.7.9 Calculation of nodal heat transfer terms
26.8 Verification tests
26.8.1 Neutron kinetics model
26.8.2 Thermal-hydraulic model
26.8.3 Fuel bowing model
26.9 Dynamic safety analysis of SABR#2
26.9.1 Accident scenarios and corrective actions
26.9.2 Accident results
26.9.3 Neutronic coupling
26.10 Discussion
27 Space-dependent dynamics calculation model for a sodium pool-cooled fast transmutation reactor (SABR#2)
27.1 Neutron kinetics model
27.1.1 Calculation of nodal kinetics terms
27.1.2 Calculation of feedback effects
27.1.3 Modeling the core
27.1.4 Thermal-hydraulic model
27.1.5 Modeling the heat exchanger
27.1.6 Modeling the sodium pool
27.1.7 Thermal property data and empirical correlations
27.1.8 Calculation of nodal heat transfer terms
27.2 Verification tests
27.2.1 Neutron kinetics model
27.2.2 Thermal-hydraulic model
27.2.3 Fuel bowing model
27.3 Dynamic safety analysis
27.3.1 Accident scenarios and corrective actions
27.3.2 Accident analyses
27.3.3 Neutronic coupling
27.4 Discussion
28 The panacea of just harvesting “free” green energy?
29 Summary, discussion, and recommendations
Further reading: Georgia Tech Fusion–Fission Hybrid Papers
Glossary for “Fusion–Fission Hybrid Reactors”
References for “Fusion–Fission Hybrids”
Topical Summary
Other volumes in this series
Back Cover