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Stress corrosion cracking in light water reactors : good practices and lessons learned.
"The average operating age of existing nuclear power plants (NPPs) is increasing and safety and performance of these ageing NPPs must be achieved by effectively managing material degradations within an acceptable level. Stress corrosion cracking (SCC) is one of significant material degradations...
| Clasificación: | Libro Electrónico |
|---|---|
| Autor Corporativo: | |
| Otros Autores: | , |
| Formato: | Electrónico eBook |
| Idioma: | Inglés |
| Publicado: |
Vienna :
International Atomic Energy Agency,
2011.
|
| Colección: | IAEA nuclear energy series ;
no. NP-T-3.13. |
| Temas: | |
| Acceso en línea: | Texto completo |
MARC
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| 050 | 4 | |a TK9203.L45 |b S77 2011 | |
| 082 | 0 | 4 | |a 621.4834 |
| 049 | |a UAMI | ||
| 245 | 0 | 0 | |a Stress corrosion cracking in light water reactors : |b good practices and lessons learned. |
| 260 | |a Vienna : |b International Atomic Energy Agency, |c 2011. | ||
| 300 | |a 1 online resource (100 pages) : |b illustrations (chiefly color). | ||
| 336 | |a text |b txt |2 rdacontent | ||
| 337 | |a computer |b c |2 rdamedia | ||
| 338 | |a online resource |b cr |2 rdacarrier | ||
| 490 | 1 | |a IAEA nuclear energy series, |x 1995-7807 ; |v no. NP-T-3.13 | |
| 500 | |a "September 2011. STI/PUB/1522"--PDF t.p. verso. | ||
| 500 | |a "The IAEA officers responsible for this report were K.S. Kang, and L. Kupca of the Division of Nuclear Power"--PDF Foreword page. | ||
| 504 | |a Includes bibliographical references. | ||
| 520 | |a "The average operating age of existing nuclear power plants (NPPs) is increasing and safety and performance of these ageing NPPs must be achieved by effectively managing material degradations within an acceptable level. Stress corrosion cracking (SCC) is one of significant material degradations for major components of both pressurized water reactors (PWRs) and boiling water reactors (BWRs) and is still an important outstanding technical issue. This publication provides general descriptions of degradation mechanisms of different types of SCC which are concerned to systems, structures and components (SSCs) in PWR and BWR. It includes examples of good practices in preventing, mitigating and repairing SCC damages and summarizes related national and international research and development programmes. Practical operational experience and practices in Member States are also presented in this overview"--Provided by publisher. | ||
| 588 | 0 | |a Print version record. | |
| 538 | |a System requirements: Adobe Acrobat Reader for Windows. | ||
| 505 | 0 | |a Introduction -- Mechanisms and major contributors to stress corrosion cracking -- Operating experiences -- Ageing management application on stress corrosion cracking -- Inspection -- Mitigation and repair methods -- Component replacement including prevention methods for new systems and components -- Summary on managing stress corrosion cracking. | |
| 590 | |a Knovel |b ACADEMIC - Civil Engineering & Construction Materials | ||
| 590 | |a Knovel |b ACADEMIC - Metals & Metallurgy | ||
| 650 | 0 | |a Light water reactors |x Corrosion. | |
| 650 | 0 | |a Stress corrosion. | |
| 650 | 6 | |a Réacteurs à eau légère |x Corrosion. | |
| 650 | 6 | |a Corrosion sous tension. | |
| 650 | 7 | |a Light water reactors |x Corrosion. |2 fast |0 (OCoLC)fst00998582 | |
| 650 | 7 | |a Stress corrosion. |2 fast |0 (OCoLC)fst01134948 | |
| 700 | 1 | |a Kang, K-S. | |
| 700 | 1 | |a Kupca, L. | |
| 710 | 2 | |a International Atomic Energy Agency. | |
| 776 | 0 | 8 | |i Print version: |t Stress corrosion cracking in light water reactors. |d Vienna, Austria : International Atomic Energy Agency, 2011 |z 9789201172105 |w (OCoLC)779243783 |
| 830 | 0 | |a IAEA nuclear energy series ; |v no. NP-T-3.13. | |
| 856 | 4 | 0 | |u https://appknovel.uam.elogim.com/kn/resources/kpSCCLWRG3/toc |z Texto completo |
| 994 | |a 92 |b IZTAP | ||