Closed Nuclear Fuel Cycle with Fast Reactors

Closed Nuclear Fuel Cycle with Fast Reactors: Handbook of Russian Nuclear Power provides unique insights into research and practical activities from leading Russian experts. It presents readers with unprecedented insight and essential knowledge surrounding nuclear fast reactor technologies, as well as novel methods to close the nuclear fuel cycle to achieve cleaner, more environmentally friendly, and more efficient nuclear power. Using the Proryv Project as a framework, the book's contributors provide detailed descriptions of technologies in development in Russia, allowing readers from around the globe to gain a thorough understanding which they can then apply to their own research and practice.

Nuclear engineers and technologists of fast reactors, advanced reactors and fuel cycles will use this book as a guide to inform new technology development. They will be able to use the experiences from the Proryv Project to drive fast reactor development with closed fuel cycles for the future.

Autorentext
Evgeny Adamov is an honored scientist of the Russian Federation, Chairman of the Scientific and Technical Council of Rosatom State Corporation and author of more than 200 scientific publications and patents.

Since 2012, research on the development of a new technological platform for nuclear power has been carried out as part of the Proryv” project, initiated by Professor Adamov and implemented under his scientific supervision. In the 1980s, E.O. Adamov launched scientific and technical activities in Russia to develop a new (fifth) generation nuclear technologies for large-scale nuclear power with closed nuclear fuel cycle (CNFC) and fast reactors, which allows to overcome the basic modern problems of nuclear energy production.

Inhalt

1. Introduction
   
   Part I. Global power generation and the role of nuclear power engineering
   
   2. Power generation and sustainable development
   3. Role of nuclear power engineering in the Russian fuel and energy industry
      
      Part II. Basic components of a new technology platform for nuclear power engineering
   4. Fuel cycles of nuclear power engineering
   5. Fuel supply
   6. Prevention of severe reactivity-related accidents
   7. Prevention of severe heat removal accidents
   8. Codes for development and safety analysis of reactor plants
   9. SNF and RW handling as a risk factor for the public
   10. Radiation and radiological equivalence of RW for two-component nuclear power engineering
   11. Technology support of the non-proliferation regime and conditions for export of the CNFC and FNR technologies
   12. Economic competitiveness of innovative nuclear power engineering
       
       Part III. Nuclear fuel and closing of the nuclear fuel cycle
       13. Uranium and uranium-plutonium nuclear fuel
   13. Dense nuclear fuel for fast reactors
   14. Development of nitride fuel within the framework of Breakthrough Project
   15. Mixed oxide fuel for fast reactors
   16. REMIX fuel
   17. Adaptation of uranium-plutonium fuel fabrication technologies
   18. Usage of the industry-specific fuel infrastructure
   19. Structural materials for fuel element claddings
   20. SNF processing technologies
   21. Radioactive waste management
       
       Part IV. Advanced reactor technologies and the nuclear power engineering infrastructure
       23. New generation reactor technologies within the framework of Generation IV International Forum
   22. Development of technologies based on fast reactors
   23. Fast reactors within the framework of Breakthrough Work Stream
   24. Thermal reactors
   25. Expansion of the nuclear power engineering application scope
   26. Alternative reactor technologies
   27. Superconducting power transmission technologies
   28. Experimental facilities of nuclear power engineering
   29. Digitalization in nuclear power engineering
   30. Regulatory framework for the modern and future nuclear power engineering
       
       Part V. Strategic guidelines for establishment of two-component nuclear power engineering
       33. Optimal development scenarios for the Russian nuclear power engineering
   31. Comparative analysis of the Russian nuclear power engineering development scenarios
   32. Russian nuclear power engineering development variants for different integral capacity growth scenarios
       
       Conclusion
       Appendix
   33. Potential biological hazard (PBH) of significant radionuclides in the nuclear power engineering waste from thermal and fast reactors in 2100
   34. PBH of significant radionuclides in the nuclear power engineering waste from thermal and fast reactors subsequent to storage for 100 to 1000 years starting with 2100
   35. PBH of natural uranium with the total mass of 541.7 thous. tons
   36. Characteristics of fuel campaigns for light-water reactors in the closed NFC
   37. Basic technical characteristics of power units with fast reactors