Closed nuclear fuel cycle with fast reactors : white book of Russian nuclear power /

Detalles Bibliográficos
Clasificación:Libro Electrónico
Otros Autores: Adamov, Evgenei O.
Formato: Electrónico eBook
Idioma:Inglés
Publicado: [S.l.] : Academic Press, 2022.
Temas:
Reactor fuel reprocessing.
Fast reactors.
Combustibles nucl�eaires irradi�es > Traitement.
R�eacteurs rapides.
Fast reactors
Reactor fuel reprocessing
Acceso en línea:Texto completo
Tabla de Contenidos:
  • Front cover
  • Half title
  • Title
  • Copyright
  • Contents
  • Preface
  • Introduction
  • Establishment of nuclear power
  • Potential of nuclear power
  • Current state of global nuclear power
  • Problems of nuclear power
  • Development of the safe growth strategy for nuclear power
  • Basic principles of Strategy-2000
  • Alternative approaches to the nuclear power strategy
  • Progress of Strategy-2000 implementation
  • Strategy-2000 today
  • Part I Global power generation and the role of nuclear power engineering
  • Chapter 1 Power generation and sustainable development
  • 1.1 Modern energy sources
  • 1.2 Current peculiarities of energy consumption growth
  • 1.3 Fossil organic fuel
  • 1.4 Resource-related limitations of organic-based power engineering
  • 1.5 Environmental restrictions of organic-based power engineering
  • 1.6 Mineral nuclear fuel
  • 1.7 Renewable energy sources
  • 1.8 Thermonuclear fusion energy
  • 1.9 Role of radiation risks in nuclear power and human-induced risks for the public
  • Chapter 2 Role of nuclear power in the Russian fuel and energy industry
  • 2.1 State of nuclear power in Russia
  • 2.2 Forecast of the Energy Research Institute of the Russian Academy of Sciences-2016
  • 2.3 Estimates of nuclear power development in the world
  • 2.4 Competitiveness of nuclear power in Russia
  • Part II Basic components of a new technology platform for nuclear power engineering
  • Chapter 3 Fuel cycles of nuclear power
  • 3.1 Classification of nuclear fuel cycles
  • 3.2 Open nuclear fuel cycle
  • 3.3 Closed nuclear fuel cycle
  • 3.4 Tasks solved in the closed NFC
  • Chapter 4 Fuel supply
  • 4.1 Effect of burnup depth
  • 4.2 Role of uranium-plutonium fuel for thermal reactors
  • 4.3 Systemic evaluation of the Russian nuclear power development scenarios with and without the use of REMIX fuel for VVERs.
  • Chapter 5 Prevention of severe reactivity-related accidents
  • 5.1 Chernobyl catastrophe
  • 5.2 Dense fuel as a nuclear safety factor
  • 5.3 Heavy coolant as a nuclear safety factor
  • Chapter 6 Prevention of severe heat removal accidents
  • 6.1 Accident at EBR-1
  • 6.2 Accident at Three Mile Island NPP (USA)
  • 6.3 Accident at Mayak PA (South Ural, Russia)
  • 6.4 Fukushima catastrophe (Japan)
  • 6.5 Heavy coolant as a factor for prevention of severe heat removal accidents and explosions at NPPs
  • 6.6 Primary circuit air heat exchanger for residual heat removal
  • 6.7 Reactor designs preventing heat removal accidents
  • Chapter 7 Codes for development and safety analysis of reactor plants
  • 7.1 Design codes
  • 7.2 New generation codes
  • Chapter 8 SNF and RW handling as a risk factor for the public
  • 8.1 Radiation-equivalent RW management principle
  • 8.2 Transmutation of minor actinides
  • 8.3 Transmutation nuclear fuel cycle
  • Chapter 9 Radiation and radiological equivalence of radioactive waste in two-component nuclear power engineering
  • 9.1 Equating lifetime radiation risks of possible cancer from RW and natural raw materials
  • 9.2 Impact of uncertainty in the parameters of the annual radiation risk models on achievement of radiological equivalence in two-component nuclear energy
  • 9.3 Uncertainty in the background morbidity and mortality rates
  • 9.4 Effect of uncertainty of radiation doses magnitude on the radiological equivalence achievement
  • Chapter 10 Technology support of the nonproliferation regime and conditions for export of the CNFC and FNR technologies
  • Chapter 11 Economic competitiveness of innovative nuclear power
  • 11.1 Requirements for competitiveness of FNRs with the CNFC
  • 11.2 Effect of load following on the NPP economy
  • Part III Nuclear fuel and closing of the nuclear fuel cycle.
  • Chapter 12 Uranium and uranium-plutonium nuclear fuel
  • 12.1 Uranium fuel
  • 12.2 Uranium-plutonium nuclear fuel
  • Chapter 13 Dense nuclear fuel for fast reactors
  • 13.1 Metallic fuel
  • 13.2 Carbide fuel
  • 13.3 Nitride fuel international experience
  • 13.4 Domestic experience in nitride fuel development prior to Proryv Project launching
  • Chapter 14 Development of nitride fuel within the framework of Proryv Project
  • 14.1 Requirements for the design of nitride fuel rod
  • 14.2 Nitride manufacturing technologies
  • 14.3 Nitride fuel studies
  • 14.3.1 Reactor testing
  • 14.4 Development of methods, codes, and criteria for substantiation of fuel performance
  • Chapter 15 Mixed oxide fuel for fast reactors
  • 15.1 Pellet technology
  • 15.2 Vibration compaction technology
  • 15.3 Experience of MOX fuel use in fast reactors
  • 15.4 Industrial production of MOX fuel
  • Chapter 16 Remix fuel
  • 16.1 Modeling of nuclear fuel cycles
  • 16.2 Manufacturing of the pilot batch of REMIX fuel rods
  • 16.3 Tests of REMIX fuel in MIR reactor
  • 16.4 Reprocessing of irradiated REMIX fuel
  • Chapter 17 Adaptation of uranium-plutonium fuel fabrication technologies
  • Chapter 18 Usage of the industry-specific fuel infrastructure
  • 18.1 FSUE "Mayak PA" ("Paket" on RT-1, RT-1)
  • 18.2 FSUE "MCP" (MOX, pilot demonstration facility)
  • 18.3 JSC "Siberian Chemical Combine" (KEU-1, KEU-2, FRM)
  • 18.4 JSC "SSC RIAR"
  • 18.5 JSC "VNIINM"
  • Chapter 19 Structural materials for fuel rod claddings
  • 19.1 Studies for substantiation of fuel burnup increase
  • 19.2 Studies within the framework of Proryv Project
  • 19.3 Bench testing of dummy fuel rods (dummy fragments) including spacing elements (small-scale liquid-metal benches)
  • corrosion in lead
  • Chapter 20 SNF processing technologies
  • 20.1 Requirements for the SNF processing technology in the CNFC.
  • 20.2 Existing capacities for processing of SNF from thermal and fast reactors
  • 20.3 Hydro-metallurgical technology for processing of SNF from thermal and fast reactors
  • 20.4 Pyrochemical SNF processing technology
  • 20.5 PH-process is a combined (pyro + hydro) processing technology for SNF from fast reactors
  • 20.6 Americium and curium extraction and separation
  • 20.7 SNF processing with the use of plasma separation
  • Chapter 21 Radioactive waste management
  • 21.1 SNF and HLW transportation
  • 21.2 SNF and HLW storage
  • 21.3 Radioactive waste generated in the course of NPP operation
  • 21.4 Radioactive waste from SNF processing
  • 21.5 HLW vitrification equipment
  • 21.6 RW from the production facilities with increased plutonium content (as exemplified by PDEC nitride nuclear fuel fabrication module)
  • 21.7 Disposal of radioactive waste
  • Part IV Advanced reactor technologies and the nuclear power engineering infrastructure
  • Chapter 22 New generation reactor technologies within the framework of Generation IV International Forum
  • Chapter 23 Development of technologies based on fast reactors
  • 23.1 Fast reactor development stages in Russia
  • 23.2 BN-800 reactor and establishment of the closed NFC
  • Chapter 24 Fast reactors within the framework of Proryv Project framework
  • 24.1 Power unit with BREST-OD-300 pilot demonstration reactor plant
  • 24.2 Power unit with sodium-cooled BN-1200 reactor
  • 24.3 Conceptual design of the IPC with BR-1200
  • Chapter 25 Thermal reactors
  • 25.1 Light-water reactors
  • 25.2 Spectral regulation
  • 25.3 VVER-S reactor technology
  • 25.4 VVER-SKD reactor technology
  • Chapter 26 Expansion of the nuclear power application scope
  • 26.1 Prospects for medium-capacity NPPs
  • 26.2 Prospects for low-capacity NPPs
  • 26.3 Role of nuclear-powered heat supply.
  • 26.4 Opportunities for nuclear power installations in power-intensive industry sectors
  • Chapter 27 Alternative reactor technologies
  • 27.1 Molten salt reactors
  • 27.2 Fast reactors with the open NFC and TerraPower project
  • 27.3 Subcritical accelerator-driven systems
  • 27.4 Peculiarities of accelerator-driven systems
  • Chapter 28 Superconducting power transmission technologies
  • 28.1 Prospects for superconducting technologies
  • 28.2 Possible levels of power transmitted along the long direct current line
  • 28.3 Energy losses in the line
  • 28.4 Cooling of the line with determination of the maximum distance between cryogenic stations
  • 28.5 Cooling schemes for HTSC cable lines
  • Chapter 29 Experimental facilities of nuclear power
  • 29.1 Set of BFS test facilities
  • 29.2 Refurbishment of BOR-60 reactor
  • 29.3 Multipurpose research reactor MBIR
  • Chapter 30 Digitalization in nuclear power
  • 30.1 Digital technologies for modeling of NPE facilities
  • 30.2 Digital technologies for nuclear facility development and life cycle management
  • Chapter 31 Regulatory framework for the modern and future nuclear power
  • 31.1 Regulatory framework for nuclear power in the Russian Federation
  • 31.2 Peculiarities of the new nuclear power technology platform projects from the viewpoint of legal regulation
  • 33.3 Regulatory framework analysis and improvement
  • Part V Strategic guidelines for establishment of two-component nuclear power engineering
  • Chapter 32 Optimal development scenarios for the Russian nuclear power
  • 32.1 Basic provisions of scenario analysis
  • 32.2 Source data for the scenario analysis
  • Chapter 33 Comparative analysis of the Russian nuclear power development scenarios
  • 33.1 The initial Russian nuclear power development scenario based on the existing technologies (Variant 0).

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