Nuclear Fuel Cycle Science and Engineering

by Ian Crossland (Editor)

Overview

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. - 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

Product Details

ISBN-13:	9780857096388
Publisher:	Woodhead Publishing, Limited
Publication date:	09/21/2012
Series:	Woodhead Publishing Series in Energy
Sold by:	Barnes & Noble
Format:	eBook
Pages:	648
File size:	13 MB
Note:	This product may take a few minutes to download.

About the Author

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.

Table of Contents

Contributor contact details Woodhead Publishing Series in Energy National Nuclear Laboratory Part I: Introduction to the nuclear fuel cycle Chapter 1: Nuclear power: origins and outlook Abstract: 1.1 The rise of nuclear power: 1938 to 1970 1.2 The fall: 1970 to the mid-1990s 1.3 The resurgence: the mid-1990s to the present day 1.4 Future trends Chapter 2: Radiological protection and the nuclear fuel cycle Abstract: 2.1 Introduction 2.2 The international system of radiological protection 2.3 International safety standards 2.4 International Atomic Energy Agency (IAEA) safety requirements and guidance for radiation protection 2.5 Radiation protection in the nuclear fuel cycle 2.6 Conclusions and future trends 2.8 Appendix: Requirements of the International Basic Safety Standards relevant to radiological safety in the nuclear fuel cycle Chapter 3: Safeguards, security, safety and the nuclear fuel cycle Abstract: 3.1 Introduction 3.2 Nuclear safeguards 3.3 Nuclear security 3.4 Nuclear safety 3.5 Conclusion and future trends 3.6 Sources of further information and advice Chapter 4: Public acceptability of nuclear technology Abstract: 4.1 Introduction 4.2 Historical background 4.3 Investigating determinants of acceptability of nuclear technology 4.4 Beyond an instrumental approach to public acceptability 4.5 Future trends Chapter 5: The economics of nuclear power Abstract: 5.1 Introduction 5.2 Levelised cost of electricity (LCOE) 5.3 Financing of NPPs 5.4 Conclusions 5.5 Future trends Part II: Uranium and thorium nuclear fuel cycles: materials mining, enrichment and fuel element design and fabrication Chapter 6: Mining and milling of uranium Abstract: 6.1 Introduction 6.2 Uranium mining and milling 6.3 World uranium mines 6.4 Environmental and social impacts 6.5 Secondary sources of uranium 6.6 Conclusion and future trends Chapter 7: Uranium conversion and enrichment Abstract: 7.1 Introduction 7.2 Uranium hexafluoride 7.3 Conversion 7.4 Enrichment 7.5 Uranium hexafluoride quality, sampling and analysis 7.6 Tails management 7.7 Transport cylinder management 7.8 Nuclear safeguards 7.9 Future trends Chapter 8: Development of the thorium fuel cycle Abstract: 8.1 Reasons for considering the thorium cycle 8.2 History and development of the thorium fuel cycle 8.3 Key technological features of the thorium fuel cycle and industrial challenges 8.4 Generic issues linked to the deployment of the thorium fuel cycle 8.5 Conclusion Chapter 9: Nuclear fuel assembly design and fabrication Abstract: 9.1 Introduction 9.2 Principal design features of LWR fuel assemblies 9.3 Basic reactor physics affecting fuel assembly design 9.4 Fuel rod design and fabrication 9.5 Fuel forms 9.6 Factors affecting fuel rod endurance 9.7 Future trends 9.8 Sources of further information Part III: Impact of nuclear reactor design and operation on fuel element irradiation Chapter 10: Water cooled thermal reactor designs, operation and fuel cycle Abstract: 10.1 Introduction 10.2 Main characteristic of LWRs 10.3 Pressurised water reactor (PWR) design features 10.4 Factors affecting reactivity and their impact on PWR reactor design 10.5 PWR core design 10.6 Boiling water reactor (BWR) design features 10.7 Factors affecting reactivity and their impact on BWR reactor design 10.8 BWR core and fuel assembly design 10.9 Safety features and issues 10.10 Advantages and limitations 10.11 Future trends 10.12 Sources of further information Chapter 11: CANDU nuclear reactor designs, operation and fuel cycle Abstract: 11.1 Introduction 11.2 CANDU reactor features 11.3 CANDU fuel and refuelling 11.4 CANDU reactor control and safety 11.5 Future trends Chapter 12: Gas-cooled nuclear reactor designs, operation and fuel cycle Abstract: 12.1 Introduction 12.2 Magnox reactors 12.3 The advanced gas-cooled reactor (AGR) 12.3.5 Fuel storage 12.3.6 Waste management and decommissioning 12.4 Safety features and issues 12.5 The high-temperature gas-cooled reactor (HTGR) 12.5.2 Main plant features 12.5.