Nuclear Power Reactor Designs. From History to Advances

Table of Contents

I 1. Introduction (historical thread) 2. Early Stage Reactors 3. Graphite Reactors

II 4. Pressurized Water Reactors (Gen II) 5. Boiling Water Reactors (Gen II) 6. Pressurized Water Reactors (Gen III) 7. Boiling Water Reactors (Gen III) 8. Heavy Water Reactors

III 9. Molten Salt Reactors 10. Sodium Fast Reactors 11. Lead Fast Reactors 12. High-Temperature Gas-Cooled Reactors 13. Gas-Cooled Reactors 14. Super Water Reactors

IV 15. Small Modular Reactors 16. Micro Reactors

V 17. Accelerator Drive System Reactors 18. Fusion Reactors

Authors

Jun Wang Research Associate, University of Wisconsin, Madison, USA. Dr. Jun Wang is a Research Scientist at the University of Wisconsin, Madison. He has over 10 years of experience in code development, validation, and application, and his research areas include nuclear thermal hydraulics and safety, severe accident, fuel performance, and advanced reactors. Wang has over 50 peer-review articles published on top nuclear journals and conferences. He also has over 200 peer-review experience in 20 journals and conferences, such as the International Journal of Heat and Mass Transfer, Applied Thermal Engineering, Annals of Nuclear Energy, Nuclear Technology, Nuclear Engineering and Design, and Progress in Nuclear Energy. Sola Talabi Principal, Pittsburgh Technical, Pittsburgh, Pennsylvania, USA. Dr. Sola Talabi () is a Principal with Pittsburgh Technical, a nuclear consulting firm specializing in advanced reactor design and deployment. He is also an adjunct professor of nuclear engineering at the University of Pittsburgh and the University of Michigan. Sola's experience includes design, computational numerical analysis, manufacturing, installation, and nuclear power plant components testing. His experience includes serving as Risk Manager at Westinghouse Electric Company, where he was responsible for risk awareness, assessment, and response for advanced reactors, including AP1000 and SMR. Sama Bilbao y Leon Deputy Institute Director, Institute of Neutron Physics and Reactor Technology, Karlsruhe Institute of Technology, Karlsruhe, Germany. Dr. V. H. Sanchez-Espinoza () is a nuclear engineer with a PhD from the Dresden University of Technology, Germany. He is Deputy Institute Director and Head of the Group "Reactor Physic and Dynamics" at the Institute of Neutron Physics and Reactor Technology (INR) of the Karlsruhe Institute of Technology (KIT). He has more than 20 years of experience on reactor physics, safety-related thermal hydraulics and reactor safety for research reactors and nuclear power plants of Gen-II, III, including SMR.