Closed Nuclear Fuel Cycle with Fast Reactors

Handbook of Russian Nuclear Power

1st Edition - July 18, 2022
Editor: Evgeny Adamov
Language: English
Paperback ISBN:
9 7 8 - 0 - 3 2 3 - 9 9 3 0 8 - 1
eBook ISBN:
9 7 8 - 0 - 3 2 3 - 9 9 3 0 9 - 8

Closed Nuclear Fuel Cycle with Fast Reactors: Handbook of Russian Nuclear Power provides unique insights into research and practical activities from leading Russian experts.… Read more

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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.

Cover Image
Title Page
Copyright
Table of 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
14.4 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)
33.2 Scenario for the Russian nuclear power establishment based on evolutionary development of the VVER technology with the open NFC (Variant 1)
33.3 The development scenario with SNF processing, partial closing of the NFC and usage of regenerated nuclear materials in thermal reactors (Variant 2)
33.4 FNR reactor technology development scenario with MOX fuel (Variant 3)
33.5 Development scenario with commissioning of fast reactors with increased BR on MNIT fuel (Variant 4)
33.6 Development scenario with commissioning of fast reactors with BR ∼1 based on MNIT fuel (Variant 5)
Chapter 34 Russian nuclear power development variants for different integral capacity growth scenarios
34.1 Competitiveness according to LCOE
34.2 Assurance of the required share of nuclear generation in the energy balance of the Russian Federation
34.3 Safety level maintenance for the growing system
34.4 Solution of the problems related to SNF and its processing products
34.5 Financial and economic stability
Conclusion
Appendix
References
List of abbreviations
Index

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Closed Nuclear Fuel Cycle with Fast Reactors

Handbook of Russian Nuclear Power

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Evgeny Adamov