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This item is in: Environment > Nuclear power generation

Jacket image for Nuclear fuel cycle science and engineering – Woodhead Publishing
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Nuclear fuel cycle science and engineering

Edited by I Crossland, Crossland Consulting, UK

Woodhead Publishing Series in Energy No. 37

 - provides a comprehensive and holistic review of the complete nuclear fuel cycle
 - reviews the issues presented by the nuclear fuel cycle, including radiological protection and security, public acceptance and economic analysis
 - discusses issues at the front-end of the fuel cycle, including uranium and thorium mining, enrichment and fuel design and fabrication
 - reviews the impact of reactor design on fuel irradiation, and the options available for spent fuel reprocessing and radioactive waste management

The nuclear fuel cycle is characterised by the wide range of scientific disciplines and technologies it employs. The development of ever more integrated processes across the many stages of the nuclear fuel cycle therefore confronts plant manufacturers and operators with formidable challenges. Nuclear fuel cycle science and engineering describes both the key features of the complete nuclear fuel cycle and the wealth of recent research in this important field.

Part one provides an introduction to the nuclear fuel cycle. Radiological protection, security and public acceptance of nuclear technology are considered, along with the economics of nuclear power. Part two goes on to explore materials mining, enrichment, fuel element design and fabrication for the uranium and thorium nuclear fuel cycle. The impact of nuclear reactor design and operation on fuel element irradiation is the focus of part three, including water and gas-cooled reactors, along with CANDU and Generation IV designs. Finally, part four reviews spent nuclear fuel and radioactive waste management.

With its distinguished editor and international team of expert contributors, Nuclear fuel cycle science and engineering provides an important review for all those involved in the design, fabrication, use and disposal of nuclear fuels as well as regulatory bodies and researchers in this field.

ISBN 0 85709 073 9
ISBN-13: 978 0 85709 073 7
September 2012
648 pages  234 x 156mm  hardback  
£175.00 / US$300.00 / €210.00
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About the editor

Dr Ian Crossland is the Director of Crossland Consulting Ltd. Dr Crossland has over 40 years experience in the UK nuclear power industry. He is an independent consultant for the International Atomic Energy Agency (IAEA) as well as several national radioactive waste management bodies in Europe.

Titles which may also be of interest:
Advanced separation techniques for nuclear fuel reprocessing and radioactive waste treatment
Handbook of advanced radioactive waste conditioning technologies
Geological repository systems for safe disposal of spent nuclear fuels and radioactive waste
Managing nuclear projects


Contents

PART 1 INTRODUCTION TO THE NUCLEAR FUEL CYCLE
PART 1 INTRODUCTION TO THE NUCLEAR FUEL CYCLE
PART 2 URANIUM AND THORIUM NUCLEAR FUEL CYCLE: MATERIALS MINING, ENRICHMENT AND FUEL ELEMENT DESIGN AND FABRICATION
PART 3 IMPACT OF NUCLEAR REACTOR DESIGN AND OPERATION ON FUEL ELEMENT IRRADIATION
PART 4 SPENT NUCLEAR FUEL AND RADIOACTIVE WASTE MANAGEMENT

PART 1 INTRODUCTION TO THE NUCLEAR FUEL CYCLE

PART 1 INTRODUCTION TO THE NUCLEAR FUEL CYCLE

Nuclear power: origins and outlook
I Crossland, Crossland Consulting, UK
 - The rise of nuclear power: 1938 to 1970
 - The fall: 1970 to mid 1990s
 - The resurgence: mid 1990s to present day
 - Future trends
 - References

Radiological protection in the nuclear fuel cycle
G Linsley, Private Consultant (Formerly Head, Waste Safety Section, International Atomic Energy Agency, Vienna), UK
 - Introduction
 - The international system of radiological protection
 - International safety standards
 - International Atomic Energy Agency (IAEA) safety requirements and guidance for radiation protection
 - Radiation protection in the nuclear fuel cycle
 - Conclusion and future trends
 - References

Safeguards, security and safety in the nuclear fuel cycle: The 3S concept
D Schriefer, Consultant (formerly Director International Atomic Energy Agency (IAEA) safeguards), Austria
 - Introduction
 - Nuclear safeguards
 - Nuclear security
 - Nuclear safety
 - Conclusion and future trends
 - Sources of further information and advice
 - References

Public acceptability of nuclear technology
J Schröder, University of Antwerp and Belgian Nuclear Research Centre SCK•CEN, and A Bergmans, University of Antwerp, Belgium
 - Introduction
 - Historical background
 - Investigating determinants of acceptability of nuclear technology
 - Beyond an instrumental approach to public acceptability
 - Future trends
 - Sources of further information
 - References

The economics of nuclear power
I Crossland, Crossland Consulting, UK
 - Introduction
 - Levelised cost of electricity (LCOE)
 - Financing of nuclear power plants (NPPs)
 - Conclusions
 - Future trends
 - Sources of further information
 - References

PART 2 URANIUM AND THORIUM NUCLEAR FUEL CYCLE: MATERIALS MINING, ENRICHMENT AND FUEL ELEMENT DESIGN AND FABRICATION

Mining and milling of uranium
I Hore-Lacy, World Nuclear Association, UK
 - Introduction
 - Uranium mining and milling
 - World uranium mines
 - Environmental and social impacts
 - Secondary sources of uranium
 - Conclusion and future trends
 - Sources of further information

Uranium conversion and enrichment for nuclear power generation
J Wilks, URENCO UK Limited, UK
 - Introduction
 - Uranium hexafluoride
 - Conversion
 - Enrichment
 - Uranium hexafluoride quality, sampling and analysis
 - Tails management
 - Transport cylinder management
 - Nuclear safeguards
 - Future trends
 - Sources of further information

Development of the thorium fuel cycle
D Greneche, Nuclear Consulting, and M Chhor, AREVA NP, France
 - Reasons for considering the thorium cycle
 - History and development of the thorium fuel cycle
 - Key technological features of the thorium fuel cycle and industrial challenges
 - Generic issues linked to the deployment of the thorium fuel cycle
 - Conclusion
 - References

Nuclear fuel assembly design and fabrication
W Wiesenack, Institutt for energiteknikk, Norway
 - Introduction
 - Principal design features of light water reactor (LWR) fuel assemblies
 - Basic reactor physics affecting fuel assembly design
 - Fuel rod design and fabrication
 - Fuel forms
 - Factors affecting fuel rod endurance
 - Future trends
 - Sources of further information
 - References

PART 3 IMPACT OF NUCLEAR REACTOR DESIGN AND OPERATION ON FUEL ELEMENT IRRADIATION

Water cooled thermal reactor designs, operation and fuel cycle
N Buttery, EDF Energy, UK
 - Introduction
 - Main characteristic of light water reactors (LWRs)
 - Pressurised water reactor (PWR) design features
 - Factors affecting reactivity and their impact on PWR design
 - PWR core design
 - Boiling water reactor (BWR) design features
 - Factors affecting reactivity and their impact on BWR reactor design
 - BWR core and fuel assembly design
 - Safety features and issues
 - Advantages and limitations
 - Future trends
 - Sources of further information
 - References

CANDU nuclear reactor designs, operation and fuel cycle
P G Boczar, Independent Consultant (formerly Director, Reactor Core Technology Division, Chalk River Laboratories, AECL) Canada
 - Introduction
 - CANDU reactor features
 - CANDU fuel and refuelling
 - Reactor control and safety
 - Future trends
 - Sources of further information
 - References

Gas-cooled nuclear reactor designs, operation and fuel cycle
J Dawson, Radiological Analysis Consultant (formerly with edF Energy), UK, and M Phillips, Nympsfield Nuclear Ltd, UK
 - Introduction
 - Magnox reactors
 - The advanced gas cooled reactor (AGR)
 - Safety features and issues
 - The high temperature gas cooled reactor (HTGR)
 - Acknowledgements
 - References

Generation IV nuclear reactor designs, operation and fuel cycle
N Cerullo, University of Pisa, Italy, and G Lomonaco, University of Genova, Italy
 - Introduction
 - Innovative fuel cycles and sustainability
 - The Generation IV initiative
 - Crosscutting Generation IV research and development on fuel cycles, fuels and materials, and proliferation resistance
 - The very high temperature reactor (VHTR) and its fuel cycle
 - The supercritical water reactor (SCWR) and its fuel cycle
 - The molten salt reactor (MSR) and its fuel cycle
 - The sodium cooled fast reactor (SFR) and its fuel cycle
 - The lead cooled fast reactor (LFR) and its fuel cycle
 - The gas cooled fast reactor (GFR) and its fuel cycle
 - Future trends
 - Sources of further information and advice
 - References

Understanding and modelling fuel behaviour under irradiation
G Rossiter, National Nuclear Laboratory, UK
 - Introduction
 - Description of important phenomena
 - Modelling fuel behaviour under irradiation
 - Sources of further information and advice
 - References

PART 4 SPENT NUCLEAR FUEL AND RADIOACTIVE WASTE MANAGEMENT

Management of spent nuclear fuel from power reactors
Z Losavic, International Atomic Energy Agency (IAEA), Austria
 - Types of nuclear reactors and nuclear fuel arisings
 - International initiatives in spent fuel management
 - Characteristics of spent nuclear fuel
 - Spent fuel management strategies
 - Spent fuel storage
 - Spent fuel disposal
 - Spent fuel reprocessing and recycling
 - High level radioactive waste (HLW) storage and disposal
 - References

Reprocessing of spent oxide fuel from nuclear power reactors
P Netter, AREVA
 - Introduction: closed and open cycles
 - Reprocessing targets and constraints
 - Plutonium and uranium refining by extraction (PUREX)
 - Reprocessing plants
 - Reprocessing industrial organization
 - Closed cycle
 - Future trends
 - Sources of further information and advice

Partitioning and transmutation of spent nuclear fuel and radioactive waste
M Salvatores, Senior Scientific Advisor, Nuclear Energy Directorate CEA (France) and Idaho National Laboratory, USA
 - Introduction
 - Physics principles of transmutation
 - Transmutation in different types of reactors
 - Implementation scenarios
 - Potential benefits of partitioning and transmutation (P&T) for a repository
 - Future trends and research and development challenges
 - Conclusion
 - Acknowledgement
 - References

Disposal of radioactive waste
I Crossland, Crossland Consulting, UK
 - Introduction
 - Nature of radioactive waste
 - Pre-disposal
 - Framework for disposal
 - Modern disposal practice
 - Future trends
 - Sources of further information and advice
 - References

Packaging and transport of radioactive material in the nuclear fuel cycle
R B Pope, Consultant (Formerly Head of Transport Safety Unit, International Atomic Energy Agency, Vienna), USA
 - Introduction
 - Safety and security in the packaging and transport of radioactive material
 - Governing international regulatory security principles and guidance in radioactive materials packaging and transport
 - Regulatory requirements for packages and transport
 - Transport experience and operations
 - Current technologies and future trends
 - Sources of further information and advice
 - Acknowledgement
 - References

Appendix Co-operation in the field of nuclear power: An overview of non-commercial international nuclear power organisations
J Mathieson, Head of International Relations, Nuclear Decommissioning Authority, UK
 - Introduction
 - Non-commercial international nuclear power agencies
 - International conferences
 - International conventions
 - Sources of further information

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