Physics of Nuclear Reactors

1st Edition - May 19, 2021
Imprint: Academic Press
Editors: P. Mohanakrishnan, Om Pal Singh, K. Umasankari
Language: English
Paperback ISBN:
9 7 8 - 0 - 1 2 - 8 2 2 4 4 1 - 0
eBook ISBN:
9 7 8 - 0 - 1 2 - 8 2 2 4 4 2 - 7

Physics of Nuclear Reactors presents a comprehensive analysis of nuclear reactor physics. Editors P. Mohanakrishnan, Om Pal Singh, and Kannan Umasankari and a team of expert co… Read more

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Physics of Nuclear Reactors presents a comprehensive analysis of nuclear reactor physics. Editors P. Mohanakrishnan, Om Pal Singh, and Kannan Umasankari and a team of expert contributors combine their knowledge to guide the reader through a toolkit of methods for solving transport equations, understanding the physics of reactor design principles, and developing reactor safety strategies. The inclusion of experimental and operational reactor physics makes this a unique reference for those working and researching nuclear power and the fuel cycle in existing power generation sites and experimental facilities. The book also includes radiation physics, shielding techniques and an analysis of shield design, neutron monitoring and core operations.

Those involved in the development and operation of nuclear reactors and the fuel cycle will gain a thorough understanding of all elements of nuclear reactor physics, thus enabling them to apply the analysis and solution methods provided to their own work and research. This book looks to future reactors in development and analyzes their status and challenges before providing possible worked-through solutions.

Cover image: Kaiga Atomic Power Station Units 1 – 4, Karnataka, India. In 2018, Unit 1 of the Kaiga Station surpassed the world record of continuous operation, at 962 days. Image courtesy of DAE, India.

Cover image
Title page
Table of Contents
Copyright
Contributors
Foreword
Preface
Acknowledgments
Chapter 1: Introduction
Abstract
1.1: Introduction
1.2: The atom and its nucleus
1.3: The nucleus
1.4: Nuclide number density
1.5: Nuclear stability
1.6: Binding energy
1.7: Radioactivity
1.8: Nuclear models
1.9: Nuclear energy levels
1.10: Nuclear reactions
1.11: Neutron interactions
1.12: Neutron elastic scattering
1.13: Neutron inelastic scattering
1.14: Radiative capture
1.15: (n, x) reaction
1.16: Fission
1.17: Probabilities of nuclear reactions
1.18: Variation of cross-section with energy
1.19: Compound nucleus reaction versus direct reaction
1.20: Cross-section data representation and resonance formalism
1.21: Fission mechanism
1.22: Fission neutrons
1.23: Energy released in fission
1.24: Neutron chain reaction and generations
1.25: Concept of a nuclear reactor
1.26: Thermal reactor and fast reactor
1.27: Spatial dependence of the neutrons in a reactor
1.28: Basic physics of reactor design
1.29: The reactor-power
1.30: Summary
1.31: Exercise problems
Chapter 2: Nuclear data
Abstract
2.1: Introduction: Nuclear data and its importance
2.2: Nuclear data production
2.3: Nuclear data evaluation
2.4: Nuclear data processing
2.5: Summary
2.6: Exercise problems
Chapter 3: Types of nuclear reactors
Abstract
3.1: Introduction
3.2: Classifications of nuclear reactors
3.3: Thermal neutron reactors
3.4: Fast neutron reactors
3.5: Future energy systems
3.6: Fusion reactor systems
3.7: Fission-fusion hybrids
3.8: Particle accelerators [11]
3.9: Accelerator-driven subcritical systems (ADSS)
3.10: One way coupled booster reactor concept in BARC
3.11: More topics of interest
3.12: Exercise problems
Chapter 4: Homogeneous reactor and neutron diffusion equation
Abstract
4.1: Introduction
4.2: Neutron density and flux
4.3: Neutron continuity equation
4.4: Transport cross-section
4.5: Fick's law of neutron diffusion
4.6: Diffusion equation
4.7: Neutron diffusion in nonmultiplying media
4.8: Neutron diffusion in a multiplying media
4.9: Reflected infinite slab reactor
4.10: Neutron life cycle in a thermal reactor
4.11: Slowing down equation
4.12: Neutron thermalization
4.13: Two-group diffusion theory
4.14: Multigroup diffusion equation
4.15: Numerical solution of the diffusion equation in 1-D slab geometry
4.16: Summary and more topics of interest
4.17: Exercise problems
Chapter 5: Methods of solving neutron transport equation
Abstract
5.1: Introduction
5.2: Assumptions in the neutron transport theory
5.3: Neutron-nucleus interaction cross-sections
5.4: The neutron transport equation
5.5: Solution to the neutron transport equation
5.6: Numerical solution to the neutron transport equation
5.7: The synthetic acceleration schemes
5.8: The integral form of transport equation
5.9: Solution to the integral transport equation
5.10: Method of characteristics approach
5.11: Monte Carlo neutron transport
5.12: More topics of interest
5.13: Exercise problems
Chapter 6: Fuel burnup, fuel management, and fuel cycle physics
Abstract
6.1: Introduction
6.2: Fuel burnup and its effects
6.3: Bateman equation and solutions
6.4: In-core fuel management
6.5: Fuel management algorithms
6.6: Long life cores
6.7: Fuel utilization
6.8: More topics of interest
6.9: Exercise problems
6.10: Additional exercises
Chapter 7: Nuclear reactor kinetics
Abstract
7.1: Introduction
7.2: Definition of important kinetics parameters
7.3: Prompt and delayed neutrons
7.4: The point kinetics equations
7.5: Kinetics of a subcritical reactor
7.6: Numerical solution of point kinetics equations
7.7: Reactivity feedback in nuclear reactors
7.8: Long irradiation reactivity effects in reactors
7.9: Reactor stability analysis
7.10: Neutronic coupling in a reactor
7.11: Xenon oscillations
7.12: Space time kinetics
7.13: Summary
A.1: Annexure
7.14: Exercise problems
Chapter 8: Nuclear reactor safety
Abstract
8.1: Introduction
8.2: Fundamental safety principles and safety framework [2, 9–11]
8.3: Safety requirements and graded approach in safety
8.4: Safety features in a NPP
8.5: Deterministic safety assessment [12–22]
8.6: Reliability analysis of safety systems [4, 23–30]
8.7: Probabilistic safety assessment: Level-1, Level-2, and Level-3. Case studies [31–54]
8.8: Uncertainty analysis in reliability and risk assessment [55–60]
8.9: Major nuclear reactor accidents
8.10: Brief history of the nuclear safety
8.11: Summary
8.12: Exercise problems
Chapter 9: Design methods and computer codes
Abstract
9.1: Introduction
9.2: Methods of neutronics analysis in thermal reactors
9.3: Methods of neutronics analyses in fast reactors
9.4: More topics of interest
Chapter 10: Experimental and operational reactor physics
Abstract
10.1: Introduction
10.2: Neutron monitoring: Neutron detectors and instruments
10.3: Neutron flux measurement using activation method
10.4: Start-up or commissioning experiments in reactors
10.5: Reactivity measurements
10.6: Low power physics experiments in thermal reactors
10.7: Reactor start-up in sodium cooled fast reactors
10.8: Failed fuel detection
10.9: Regulatory aspects and reactor experimentation and operation
10.10: Some critical/subcritical experimental facilities
10.11: More topics of interest
10.12: Exercise problems
Chapter 11: Radiation safety and radiation shielding design
Abstract
11.1: Introduction
11.2: Basic radiation physics
11.3: Radiation dosimetry
11.4: Gamma shields
11.5: Neutron shields
11.6: Reactor sources of radiation
11.7: Radioactive sources in fuel cycle facilities
11.8: Radiation dose limits for exposures
11.9: Shield design for reactors
11.10: Complementary shielding
11.11: Shield design methods in fuel cycle facilities
11.12: Summary and more topics of interest
11.13: Exercise problems
Chapter 12: Nuclear reactors of the future
Abstract
12.1: Introduction
12.2: Generation IV reactors
12.3: Small and modular reactors
12.4: Traveling wave reactors
12.5: Review questions
Index

P. Mohanakrishnan

Dr. Mohanakrishnan was a scientist at the Theoretical Physics Division of Bhabha Atomic Research Centre (BARC) for 13 years, and then at the Reactor Physics Division of Indira Gandhi Centre for Atomic Research (IGCAR) for 25 years. He was the Associate Director of the Reactor Physics Group at IGCAR, before becoming Adjunct Professor at, Manipal University, a position he held for 7 years. Presently, Dr. Mohanakrishnan is a consultant to the Atomic Energy Regulatory Board (AERB), Mumbai. He was recognized as a PhD guide by the University of Madras, Homi Bhabha National Institute (HBNI) and Manipal University. He was also the Dean of HBNI at IGCAR, specializing in reactor physics for the design, operation and safety of both thermal and fast reactors. He is experienced in the measurement of reactor parameters and has been involved in the development of computer codes for reactor analysis, preparation of manuals for reactor operation and guides for reactor safety.

Affiliations and expertise

Formerly at Bhabha Atomic Research Centre, Mumbai, Maharashtra; Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu, India. Specialized in design and analysis of thermal and fast neutron reactors and reactor experiments.

Om Pal Singh

Dr. Om Pal Singh has been a scientist at the Reactor Physics Division of Indira Gandhi Center for Atomic Research (IGCAR), Kalpakkam, Tamil Nadu, India for 31 years. At the time of transfer to Atomic Energy Regulatory Board (AERB), Mumbai, India, he was Head of the Reactor Physics Division in IGCAR. In AERB, he was secretary of the Board and Director of one of the Divisions for 6.5 years. Dr. Singh then became Visiting Professor at Indian Institute of Technology (IIT) Kanpur, Kanpur, UP, India for 5.5 years. He was recognized as a PhD guide by University of Madras and Bombay and co-guide at IIT-Kanpur and guided several PhD theses. He is specialized in theory and experimental work and is expert in reactor physics, deterministic safety analysis, Probabilistic Safety Analysis (PSA), Signal Processing Techniques and Regulatory Processes for nuclear and radiation facilities. He served as member of the 'Steering Committee of International Atomic Energy Agency (IAEA) on HRD in member states with nuclear power plants'. He served as 'IAEA Expert' several times in Indonesia during 1987 to 1991 and as Chief Investigator in several of the IAEA's Coordinated Research Programs including the one jointly from IAEA and European commission on core disruptive accident analysis of fast reactors. He is also holder of an Alexander Von Humboldt Foundation, German research fellowship. He served as Guest Editor (jointly with Dr. Srikumar Banerjee, Chancellor, HBNI, Mumbai, India) for a Special Issue: 'Development of Advanced Nuclear Technologies' in India published in the Elsevier journal: Progress in Nuclear Energy.

Affiliations and expertise

Formerly at Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu; Atomic Energy Regulatory Board, Mumbai, Maharashtra; Indian Institute of Technology Kanpur, Kanpur, Uttar Pradesh, India; Expertise: Nuclear Reactor Physics and Safety Design and Analysis.

K. Umasankari

Dr. Umasankari is an experienced reactor physicist and currently the Head of the Reactor Physics Design Division at the Bhabha Atomic Research Centre (BARC). She is also a senior professor and PhD guide at the Homi Bhabha National Institute (HBNI). She is specialized in thorium utilization in reactors, nuclear data physics for thorium fuel cycle and fuel cycle studies for advanced systems. She has great experience in the design and safety of thermal neutron reactor systems, specifically pressurized heavy water reactors and its advanced versions, high temperature reactors and molten salt reactors. She also has significant contributions to coupled neutronic and thermal hydraulic safety studies, design of reactor physics experiments and development of computational tools for reactor design.

Affiliations and expertise

Head, Reactor Physics Design Division, Bhabha Atomic Research Centre, Mumbai, India and Senior Professor and PhD guide at Homi Bhabha National Institute, Mumbai, India

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