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Microstructural and microchemical mechanisms controlling intergranular stress corrosion cracking in light-water-reactor systems

dc.contributor.authorBruemmer, Stephen M.en_US
dc.contributor.authorWas, Gary S.en_US
dc.date.accessioned2006-04-10T17:51:43Z
dc.date.available2006-04-10T17:51:43Z
dc.date.issued1994-10en_US
dc.identifier.citationBruemmer, Stephen M., Was, Gary S. (1994/10)."Microstructural and microchemical mechanisms controlling intergranular stress corrosion cracking in light-water-reactor systems." Journal of Nuclear Materials 216(): 348-363. <http://hdl.handle.net/2027.42/31289>en_US
dc.identifier.urihttp://www.sciencedirect.com/science/article/B6TXN-47YRKNS-2HJ/2/dcf9eaa187776b857a3e1b908e658256en_US
dc.identifier.urihttps://hdl.handle.net/2027.42/31289
dc.description.abstractThis review paper examines mechanisms controlling IGSCC in selected LWR components. Emphasis is placed on identifying material microstructures and microchemistries which promote susceptibility to premature failure. Two important examples are evaluated in some detail: stainless steel pipe cracking and primary-side SCC of alloy 600 steam generator tubing. In each case, grain boundary segregation and precipitation phenomena in these materials are reviewed and assessed relative to the mechanisms of IGSCC. This paper summarizes materials presented at the 1993 International Summer School on the Fundamentals of Radiation Damage held at the University of Illinois. A more comprehensive overview of SCC mechanisms and LWR examples was provided at the school, but will not be included in this article. Microstructural and microchemical aspects controlling IGSCC described here serve as a lead-in to the following paper focussing on how irradiation influences SCC resistance of reactor core components.en_US
dc.format.extent1844184 bytes
dc.format.extent3118 bytes
dc.format.mimetypeapplication/pdf
dc.format.mimetypetext/plain
dc.language.isoen_US
dc.publisherElsevieren_US
dc.titleMicrostructural and microchemical mechanisms controlling intergranular stress corrosion cracking in light-water-reactor systemsen_US
dc.typeArticleen_US
dc.rights.robotsIndexNoFollowen_US
dc.subject.hlbsecondlevelNuclear Engineering and Radiological Sciencesen_US
dc.subject.hlbtoplevelEngineeringen_US
dc.description.peerreviewedPeer Revieweden_US
dc.contributor.affiliationumDepartments of Nuclear Engineering and Materials Science and Engineering, University of Michigan, Ann Arbor, MI 48109, USAen_US
dc.contributor.affiliationotherMaterials Sciences Department, Pacific Northwest Laboratory, Richland, WA 99352, USAen_US
dc.description.bitstreamurlhttp://deepblue.lib.umich.edu/bitstream/2027.42/31289/1/0000195.pdfen_US
dc.identifier.doihttp://dx.doi.org/10.1016/0022-3115(94)90020-5en_US
dc.identifier.sourceJournal of Nuclear Materialsen_US
dc.owningcollnameInterdisciplinary and Peer-Reviewed


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