Screen LibraryIrradiation embrittlement of reactor pressure vessels (RPVs) in nuclear power plants /
Reactor Pressure Vessels (RPVs) contain the fuel and therefore the reaction at the heart of nuclear power plants. They are a life-determining structural component: if they suffer serious damage, the continued operation of the plant is in jeopardy. This book critically reviews irradiation embrittleme...
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| Corporate Authors: | |
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| Group Author: | |
| Published: |
Woodhead Publishing,
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| Publisher Address: | Cambridge [England] : |
| Publication Dates: |
2015. ©2015 |
| Literature type: | eBook |
| Language: | English |
| Series: |
Woodhead Publishing series in energy ;
number 26 |
| Subjects: | |
| Online Access: |
http://www.sciencedirect.com/science/book/9781845699673 |
| Summary: |
Reactor Pressure Vessels (RPVs) contain the fuel and therefore the reaction at the heart of nuclear power plants. They are a life-determining structural component: if they suffer serious damage, the continued operation of the plant is in jeopardy. This book critically reviews irradiation embrittlement, the main degradation mechanism affecting RPV steels, and mitigation routes for managing the RPV lifetime. Part I reviews RPV design and fabrication in different countries, with an emphasis on the materials required, their important properties, and manufacturing technologies. Part II then con. |
| Carrier Form: | 1 online resource (437 pages). |
| Bibliography: | Includes bibliographical references and index at the end of each chapters. |
| ISBN: |
9780857096470 0857096478 1322097682 9781322097688 |
| Index Number: | TK9202 |
| CLC: | TL3 |
| Contents: |
Cover; Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants; Copyright; Contents; Contributor contact details; Woodhead Publishing Series in Energy; Preface; Part I: Reactor pressure vessel (RPV) design and fabrication; 1 Reactor pressure vessel (RPV) design and fabrication: the case of the USA; 1.1 Introduction; 1.2 American Society of Mechanical Engineers (ASME) Code design practices; 1.3 The design process; 1.4 Reactor pressure vessel (RPV) materials selection; 1.5 Toughness requirements; 1.6 RPV fabrication processes; 1.7 Welding practices; 1.8 References. 2 Reactor pressure vessel (RPV) components: processing and properties2.1 Introduction; 2.2 Advances in nuclear reactor pressure vessel (RPV) components; 2.3 Materials for nuclear RPVs; 2.4 Manufacturing technologies; 2.5 Metallurgical and mechanical properties of components; 2.6 Conclusions; 2.7 References; 3 WWER-type reactor pressure vessel (RPV) materials and fabrication; 3.1 Introduction; 3.2 WWER reactor pressure vessel (RPV) materials; 3.3 Production of materials for components and welding techniques; 3.4 Future trends; 3.5 Sources of further information and advice. Part II: Reactor pressure vessel (RPV) embrittlement in operational nuclear power plants4 Embrittlement of reactor pressure vessels (RPVs) in pressurized water reactors (PWRs); 4.1 Introduction; 4.2 Characteristics of pressurized water reactor (PWR) reactor pressure vessel (RPV) embrittlement; 4.3 US surveillance database; 4.4 French surveillance database; 4.5 Japanese surveillance database; 4.6 Surveillance databases from other countries; 4.7 Future trends; 4.8 References; 5 Embrittlement of reactor pressure vessels (RPVs) in WWER-type reactors; 5.1 Introduction. 5.2 Characteristics of embrittlement of WWER reactor pressure vessel (RPV) materials5.3 Trend curves; 5.4 WWER surveillance programmes; 5.5 RPV annealing in WWER reactors; 5.6 RPV annealing technology; 5.7 Sources of further information and advice; 5.8 References; 6 Integrity and embrittlement management of reactor pressure vessels (RPVs) in light-water reactors; 6.1 Introduction; 6.2 Parameters governing reactor pressure vessel (RPV) integrity; 6.3 Pressure-temperature operating limits; 6.4 Pressurized thermal shock (PTS); 6.5 Mitigation methods; 6.6 Licensing considerations; 6.7 References 7 Surveillance of reactor pressure vessel (RPV) embrittlement in Magnox reactors7.1 Introduction; 7.2 History of Magnox reactors; 7.3 Reactor pressure vessel (RPV) materials and construction; 7.4 Reactor operating rules; 7.5 Design of the surveillance schemes; 7.6 Early surveillance results; 7.7 Dose-damage relationships and intergranular fracture in irradiated submerged-arc welds (SAWs); 7.8 Infl uence of thermal neutrons; 7.9 Validation of toughness assessment methodology by RPV SAW sampling; 7.10 Final remarks; 7.11 Acknowledgements; 7.12 References. |