Closed Nuclear Fuel Cycle with Fast Reactors

Handbook of Russian Nuclear Power

Specificaties
Paperback, blz. | Engels
Elsevier Science | e druk, 2022
ISBN13: 9780323993081
Rubricering
Elsevier Science e druk, 2022 9780323993081
€ 193,00
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Samenvatting

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.

Specificaties

ISBN13:9780323993081
Taal:Engels
Bindwijze:Paperback

Inhoudsopgave

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