Stress corrosion crack detection in alloy 600 in high temperature caustic.

Stress corrosion crack detection in alloy 600 in high temperature caustic.

CIVINS === Alloy 600, the material used for pressurized water reactor steam generator tubing, is susceptible to environmentally assisted stress corrosion cracking. Intergranular stress corrosion cracking (IGSCC) attacks the tubes in areas of high residual stress, and in crevice regions. No method ha...

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Main Author: Brisson, Bruce W.
Other Authors: Nuclear Engineering
Language:en_US
Published: Monterey, California. Naval Postgraduate School 2012
Online Access:http://hdl.handle.net/10945/9017
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spelling ndltd-nps.edu-oai-calhoun.nps.edu-10945-90172015-06-20T16:02:35Z Stress corrosion crack detection in alloy 600 in high temperature caustic. Brisson, Bruce W. Nuclear Engineering CIVINS Alloy 600, the material used for pressurized water reactor steam generator tubing, is susceptible to environmentally assisted stress corrosion cracking. Intergranular stress corrosion cracking (IGSCC) attacks the tubes in areas of high residual stress, and in crevice regions. No method has been successfully developed to monitor steam generator tubing in-situ for crack initiation and growth. Essentially all available published IGSCC crack growth data for alloy 600 is based on non-tubing material. Although it is very likely that the current data base is applicable to tubing processing, differences between tube and other geometries make a comparison between tubing and other data important for verification purposes. However, obtaining crack initiation and growth data from tubing is difficult due to the geometry and the thin wall thickness 2012-08-09T19:23:56Z 2012-08-09T19:23:56Z 1996 Thesis http://hdl.handle.net/10945/9017 en_US Monterey, California. Naval Postgraduate School
collection NDLTD
language en_US
sources NDLTD
description CIVINS === Alloy 600, the material used for pressurized water reactor steam generator tubing, is susceptible to environmentally assisted stress corrosion cracking. Intergranular stress corrosion cracking (IGSCC) attacks the tubes in areas of high residual stress, and in crevice regions. No method has been successfully developed to monitor steam generator tubing in-situ for crack initiation and growth. Essentially all available published IGSCC crack growth data for alloy 600 is based on non-tubing material. Although it is very likely that the current data base is applicable to tubing processing, differences between tube and other geometries make a comparison between tubing and other data important for verification purposes. However, obtaining crack initiation and growth data from tubing is difficult due to the geometry and the thin wall thickness
author2 Nuclear Engineering
author_facet Nuclear Engineering
Brisson, Bruce W.
author Brisson, Bruce W.
spellingShingle Brisson, Bruce W.
Stress corrosion crack detection in alloy 600 in high temperature caustic.
author_sort Brisson, Bruce W.
title Stress corrosion crack detection in alloy 600 in high temperature caustic.
title_short Stress corrosion crack detection in alloy 600 in high temperature caustic.
title_full Stress corrosion crack detection in alloy 600 in high temperature caustic.
title_fullStr Stress corrosion crack detection in alloy 600 in high temperature caustic.
title_full_unstemmed Stress corrosion crack detection in alloy 600 in high temperature caustic.
title_sort stress corrosion crack detection in alloy 600 in high temperature caustic.
publisher Monterey, California. Naval Postgraduate School
publishDate 2012
url http://hdl.handle.net/10945/9017
work_keys_str_mv AT brissonbrucew stresscorrosioncrackdetectioninalloy600inhightemperaturecaustic
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