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...

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Bibliographic Details
Corporate Author: International Atomic Energy Agency.
Other Authors: Kang, K-S., Kupca, L.
Format: eBook
Language: English
Published: Vienna : International Atomic Energy Agency, 2011.
Series: IAEA nuclear energy series ; no. NP-T-3.13.
Subjects:
Light water reactors > Corrosion.
Stress corrosion.
elektronické knihy
electronic books
ISBN: 9789201172105
9201172109
Physical Description: 1 online resource (100 pages) : illustrations (chiefly color).

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Table of contents

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020 |a 9789201172105  |q (pbk.) 
020 |a 9201172109  |q (pbk.) 
035 |a (OCoLC)782057836 
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. 
506 |a Plný text je dostupný pouze z IP adres počítačů Univerzity Tomáše Bati ve Zlíně nebo vzdáleným přístupem pro zaměstnance a studenty 
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. 
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 Knovel (All titles) 
650 0 |a Light water reactors  |x Corrosion. 
650 0 |a Stress corrosion. 
655 7 |a elektronické knihy  |7 fd186907  |2 czenas 
655 9 |a electronic books  |2 eczenas 
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://proxy.k.utb.cz/login?url=https://app.knovel.com/hotlink/toc/id:kpSCCLWRG3/stress-corrosion-cracking?kpromoter=marc  |y Full text 

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