Closed nuclear fuel cycle with fast reactors : handbook of Russian nuclear power / Evgeny O. Adamov.

Format:

Book

Contributor:

Adamov, Evgeny O., editor.

Language:

English

Subjects (All):

Reactor fuel reprocessing.

Fast reactors.

Fast reactors--Russia.

Nuclear energy--Research--Russia.

Nuclear energy.

Nuclear fuels--Management.

Nuclear fuels.

Physical Description:

1 online resource (468 pages)

Edition:

1st ed.

Other Title:

Handbook of Russian nuclear power

Place of Publication:

London, England : Academic Press, [2022]

Summary:

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.

Contents:

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).

33.2 Scenario for the Russian nuclear power establishment based on evolutionary development of the VVER technology with the open NFC \(Variant 1\).

Notes:

Description based on print version record.

Description based on publisher supplied metadata and other sources.

Other Format:

Print version: Adamov, Evgenei O. Closed Nuclear Fuel Cycle with Fast Reactors

ISBN:

0-323-99309-5

OCLC:

1337068668