Fusion-Fission Hybrid Nuclear Reactors

Weston M. (Bill) Stacey is emeritus Regent's Professor of Nuclear Engineering at Georgia Institute of Technology, United States. His career in nuclear science and engineering spans 60+ years of research in nuclear reactor physics and nuclear reactor design, fusion plasma physics and fusion reactor design, at Knolls Atomic Power Laboratory, Argonne National Laboratory and Georgia Tech. He led the international IAEA INTOR Workshop (USA, USSR, EU, Japan, 1977-88) project to assess the readiness of the world's fusion programs to build an experimental fusion power reactor, to evaluate the required additional R&D, and to develop the INTOR conceptual design; this project evolved into the current ITER project for the first experimental fusion reactor. He is author of more than 350 research papers and 7 books on nuclear fission and fusion physics and technology and recipient of the ANS Seaborg and Wigner Reactor Physics awards, the DOE Distinguished Associate award and two Certificates of Appreciation, the Fusion Power Assoc. Distinguished Career award, and is a lifetime member of Who's Who.

• Chapter 1: IntroductionChapter 2: Nuclear electric power productionChapter 3: Scientific basis of nuclear fission energyChapter 4: Uranium nuclear fission power fuel cycleChapter 5: Fission energy fuel resourcesChapter 6: Technological basis of nuclear fission powerChapter 7: Conversion of nuclear fission energy to electrical energyChapter 8: Advanced fission reactorsChapter 9: The Nuclear Reactor Physics, Nuclear Reactor Engineering, Plasma Physics, and Fusion Technology disciplinesChapter 10: Safety of nuclear fission power reactorsChapter 11: The nuclear fission power fuel cycleChapter 12: Scientific and technological basis of nuclear fusion powerChapter 13: Nuclear fusion power reactor studiesChapter 14: Future improvements in fusion physics and technologyChapter 15: Fusion-fission hybrid reactorsChapter 16: Principles and technical rationale of the fusion-fission hybrid breeder and burner reactorsChapter 17: Illustrative future fusion-fission hybrid reactor designsChapter 18: SABR tokamak burner fuel cycles (using fusion neutrons to fission nuclear waste and close the back end of the fission fuel cycleChapter 19: Computational models for tritium breeding ratio and fissile breeding ratiosChapter 20: Physics and engineering design constraints on fusion-fission hybridsChapter 21: Status of fusion development vis-à-vis a neutron source for FFHChapter 22: Fusion neutron enhancement of a breeding nuclear fission fuel cycleChapter 23: Using fusion neutrons to achieve a burning fission fuel cycleChapter 24: Fuel cycle methodology, summary and conclusionsChapter 25: Using fusion neutrons to achieve a breeding fission fuel cycleChapter 26: Dynamic safety analyses of FFH reactorsChapter 27: Space-dependent dynamics calculation model for a sodium pool-cooled fast transmutation reactor (SABR#2)Chapter 28: The panacea of just harvesting "free" green energy?Chapter 29: Summary, discussion, and recommendations