Materials' ageing and degradation in light water reactors : mechanisms and management / edited by K.L. Murty.

Contributor(s): Material type: TextTextSeries: Woodhead Publishing in energy ; no. 44.Publisher: Cambridge ; Philadelphia : Woodhead Publishing, 2013Description: xxi, 417 pages : illustrations ; 24 cmContent type:
  • text
Media type:
  • unmediated
Carrier type:
  • volume
ISBN:
  • 9780857092397
  • 0857092391
Subject(s): DDC classification:
  • 621.4833 23
LOC classification:
  • TK9185 .M38 2013
Online resources:
Contents:
Machine generated contents note: pt. I Fundamental ageing issues and degradation mechanisms -- 1. Overview of ageing and degradation issues in light water reactors (LWRs) / K. Ramaswamy -- 1.1. Introduction -- 1.2. Degradation mechanisms and materials ageing issues in nuclear steam supply systems (NSSS) -- 1.3. Radiation effects -- 1.4. Degradation mechanisms of specific nuclear reactor structures -- 1.5. Conclusions -- 1.6. References -- 2. Corrosion in pressurized water reactors (PWRs) / T. Couvant -- 2.1. Introduction -- 2.2. Pressurized water reactors and the main types of corrosion -- 2.3. Major components experiencing corrosion -- 2.4. Conclusion -- 2.5. References -- 3. Creep deformation of materials in light water reactors (LWRs) / I. Charit -- 3.1. Introduction -- 3.2. Standard creep equations -- 3.3. Identifying the mechanisms of creep -- 3.4. Rate controlling mechanisms and activation energy -- 3.5. Transitions in creep mechanisms -- 3.6. Modeling creep life: extrapolation of strain and rupture data -- 3.7. Case studies illustrating the role of other factors -- 3.8. Creep of zirconium alloys used for LWR cladding -- 3.9. References -- pt. II Materials ageing and degradation in particular light water reactor (LWR) components -- 4. Properties of zirconium alloys and their applications in light water reactors (LWRs) / P. Rudling -- 4.1. Introduction -- 4.2. Fuel assembly designs -- 4.3. Effects of irradiation on zirconium alloys -- 4.4. Mechanical properties of zirconium alloys -- 4.5. Corrosion of zirconium alloys -- 4.6. Dimensional stability of zirconium alloys -- 4.7. Future trends and research needs -- 4.8. Sources of further information -- 4.9. Acknowledgements -- 4.10. References -- 5. Performance and inspection of zirconium alloy fuel bundle components in light water reactors (LWRs) / R.B. Adamson -- 5.1. Introduction -- 5.2. Materials performance during normal operational conditions -- 5.3. Materials performance during accidents -- 5.4. Materials performance during interim dry storage -- 5.5. Inspection methods -- 5.6. Future trends and research needs -- 5.7. Sources of further information and advice -- 5.8. Acknowledgements -- 5.9. References -- 6. Ageing of electric cables in light water reactors (LWRs) / H.M. Hashemian -- 6.1. Introduction -- 6.2. Cable degradation issues -- 6.3. Analysis and assessment methods -- 6.4. Residual life modeling -- 6.5. Development and application of cable ageing mitigation routes -- 6.6. Sources of further information -- 6.7. References -- pt. III Materials management strategies for light water reactors (LWRs) -- 7. Materials management strategies for pressurized water reactors (PWRs) / S.S. Hwang -- 7.1. Introduction -- 7.2. Materials management strategies -- 7.3. Management techniques: development and application -- 7.4. Case studies of management strategies -- 7.5. References -- 8. Materials management strategies for VVER reactors / T.J. Katona -- 8.1. Introduction -- 8.2. Description of operating VVER reactors -- 8.3. Ageing of the VVERs -- plant operational experience -- 8.4. Ensuring safety for a long-term operation -- 8.5. Plant programmes credited for long-term operation -- 8.6. Conclusion -- 8.7. References -- 9. Materials-related problems faced by light water reactor (LWR) operators and corresponding research needs / E. Lahoda -- 9.1. Introduction -- 9.2. Fuel and cladding materials -- the first fission barrier -- 9.3. The primary system -- the second fission barrier -- 9.4. The containment structure -- the final fission barrier -- 9.5. Other nuclear reactor systems -- 9.6. References.
Tags from this library: No tags from this library for this title. Log in to add tags.
Star ratings
    Average rating: 0.0 (0 votes)

Includes bibliographical references and index.

Machine generated contents note: pt. I Fundamental ageing issues and degradation mechanisms -- 1. Overview of ageing and degradation issues in light water reactors (LWRs) / K. Ramaswamy -- 1.1. Introduction -- 1.2. Degradation mechanisms and materials ageing issues in nuclear steam supply systems (NSSS) -- 1.3. Radiation effects -- 1.4. Degradation mechanisms of specific nuclear reactor structures -- 1.5. Conclusions -- 1.6. References -- 2. Corrosion in pressurized water reactors (PWRs) / T. Couvant -- 2.1. Introduction -- 2.2. Pressurized water reactors and the main types of corrosion -- 2.3. Major components experiencing corrosion -- 2.4. Conclusion -- 2.5. References -- 3. Creep deformation of materials in light water reactors (LWRs) / I. Charit -- 3.1. Introduction -- 3.2. Standard creep equations -- 3.3. Identifying the mechanisms of creep -- 3.4. Rate controlling mechanisms and activation energy -- 3.5. Transitions in creep mechanisms -- 3.6. Modeling creep life: extrapolation of strain and rupture data -- 3.7. Case studies illustrating the role of other factors -- 3.8. Creep of zirconium alloys used for LWR cladding -- 3.9. References -- pt. II Materials ageing and degradation in particular light water reactor (LWR) components -- 4. Properties of zirconium alloys and their applications in light water reactors (LWRs) / P. Rudling -- 4.1. Introduction -- 4.2. Fuel assembly designs -- 4.3. Effects of irradiation on zirconium alloys -- 4.4. Mechanical properties of zirconium alloys -- 4.5. Corrosion of zirconium alloys -- 4.6. Dimensional stability of zirconium alloys -- 4.7. Future trends and research needs -- 4.8. Sources of further information -- 4.9. Acknowledgements -- 4.10. References -- 5. Performance and inspection of zirconium alloy fuel bundle components in light water reactors (LWRs) / R.B. Adamson -- 5.1. Introduction -- 5.2. Materials performance during normal operational conditions -- 5.3. Materials performance during accidents -- 5.4. Materials performance during interim dry storage -- 5.5. Inspection methods -- 5.6. Future trends and research needs -- 5.7. Sources of further information and advice -- 5.8. Acknowledgements -- 5.9. References -- 6. Ageing of electric cables in light water reactors (LWRs) / H.M. Hashemian -- 6.1. Introduction -- 6.2. Cable degradation issues -- 6.3. Analysis and assessment methods -- 6.4. Residual life modeling -- 6.5. Development and application of cable ageing mitigation routes -- 6.6. Sources of further information -- 6.7. References -- pt. III Materials management strategies for light water reactors (LWRs) -- 7. Materials management strategies for pressurized water reactors (PWRs) / S.S. Hwang -- 7.1. Introduction -- 7.2. Materials management strategies -- 7.3. Management techniques: development and application -- 7.4. Case studies of management strategies -- 7.5. References -- 8. Materials management strategies for VVER reactors / T.J. Katona -- 8.1. Introduction -- 8.2. Description of operating VVER reactors -- 8.3. Ageing of the VVERs -- plant operational experience -- 8.4. Ensuring safety for a long-term operation -- 8.5. Plant programmes credited for long-term operation -- 8.6. Conclusion -- 8.7. References -- 9. Materials-related problems faced by light water reactor (LWR) operators and corresponding research needs / E. Lahoda -- 9.1. Introduction -- 9.2. Fuel and cladding materials -- the first fission barrier -- 9.3. The primary system -- the second fission barrier -- 9.4. The containment structure -- the final fission barrier -- 9.5. Other nuclear reactor systems -- 9.6. References.

There are no comments on this title.

to post a comment.