Corrosion Issues in Light Water Reactors Stress Corrosion Cracking 1st Edition by D Feron, J M Olive ISBN 1845693469 9781845693466

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ISBN 10: 1845693469 
ISBN 13: 9781845693466
Author: D Feron, J M Olive

Stress corrosion cracking is a major problem in light water nuclear reactors, whether pressurised water reactors (PWRs) or boiling water reactors (BWRs). The nuclear industry needs to be able to predict the service life of these power plants and develop appropriate maintenance and repair practices to ensure safe long term operation. This important book sums up key recent research on corrosion in light water reactors and its practical applications.

The book is divided into four parts. It begins with an overview of materials degradation due to stress corrosion, corrosion potential monitoring and passivation. Part two summarises research on susceptibility of materials to stress corrosion cracking and the ways it can be initiated. The third part of the book considers stress corrosion crack propagation processes whilst the final part includes practical case studies of corrosion in particular plants. The book reviews corrosion in a range of materials such as low alloy steels, stainless steels and nickel-based alloys.

With its distinguished editor and team of contributors, Corrosion issues in light water reactors is a standard work for the nuclear industry.

Corrosion Issues in Light Water Reactors Stress Corrosion Cracking 1st Table of contents:

Part I: Overviews
1. An overview of materials degradation by stress corrosion in PWRs
 1.1 Introduction
 1.2 Nickel base alloys in PWR primary water
 1.3 Nickel base alloys on the secondary side of PWR steam generators
 1.4 Stainless steels in PWR primary circuits
 1.5 Low alloy steels
 1.6 Concluding remarks
 1.7 References

2. Corrosion potential monitoring in nuclear power environments
 2.1 Introduction
 2.2 Measurements in BWRs
 2.3 PWR primary system
 2.4 PWR secondary systems
 2.5 Summary and conclusions
 2.6 Acknowledgements
 2.7 References

3. Kinetics of passivation of a nickel-base alloy in high temperature water
 3.1 Introduction
 3.2 Experimental procedure
 3.3 Results
 3.4 Discussion
 3.5 Conclusion
 3.6 References

Part II: Stress corrosion cracking – susceptibility and initiation
4. IASCC susceptibility under BWR conditions of welded 304 and 347 stainless steels
5. The effect of lead on resistance of low alloy steel to SCC in high temperature water environments
6. Effect of cold work hardening on stress corrosion cracking of stainless steels in primary water
7. Effect of strain-path on stress corrosion cracking of AISI 304L stainless steel in PWR primary environment
8. Dynamic strain ageing of deformed nitrogen-alloyed AISI 316 stainless steels
9. Laboratory results of stress corrosion cracking of steam generator tubes in a ‘complex’ environment
10. The effect of sulphate and chloride transients on the environmentally-assisted cracking behaviour
11. Transgranular stress-corrosion cracking in austenitic stainless steels at high temperatures

Part III: Stress corrosion cracking – propagation
12. Crack growth behaviour of low-alloy steels for pressure boundary components under transient light water reactor conditions – Part I
13. Crack growth behaviour of low-alloy steels for pressure boundary components under transient light water reactor conditions – Part II
14. Effect of yield strength on stress corrosion crack propagation under PWR and BWR environments
15. Corrosion fatigue crack growth behaviour of low-alloy RPV steels at different temperatures and load ratios
16. Effect of cyclic loadings on the stress corrosion crack growth rate in alloy 600 in PWR primary water
17. Pattern recognition model to estimate intergranular stress corrosion cracking (IGSCC) at crevices
18. Fatigue crack growth in austenitic steel AISI 304L in PWR primary water at room and elevated temperatures

Part IV: Practical experience
19. Corrosion damage to 18Cr-9Ni-Ti steel after 25 years of operation in steam-water environments
20. Comprehensive investigation of the corrosion state of the heat exchanger tubes of steam generator
21. Stress corrosion cracking of a Kori 1 retired steam generator tube
22. A systematic study of the corrosion effects of the FRAMATOME CORD-UV technology

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Tags: D Feron, J M Olive, Corrosion, Water Reactors