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Irradiation assisted stress corrosion cracking of controlled purity 304L stainless steels

dc.contributor.authorCookson, J. M.en_US
dc.contributor.authorCarter, Jr. , R. D.en_US
dc.contributor.authorDamcott, D. L.en_US
dc.contributor.authorAtzmon, Michaelen_US
dc.contributor.authorWas, Gary S.en_US
dc.date.accessioned2006-04-10T15:43:33Z
dc.date.available2006-04-10T15:43:33Z
dc.date.issued1993-06en_US
dc.identifier.citationCookson, J. M., Carter, Jr., R. D., Damcott, D. L., Atzmon, M., Was, G. S. (1993/06)."Irradiation assisted stress corrosion cracking of controlled purity 304L stainless steels." Journal of Nuclear Materials 202(1-2): 104-121. <http://hdl.handle.net/2027.42/30754>en_US
dc.identifier.urihttp://www.sciencedirect.com/science/article/B6TXN-48053PH-16/2/944b7b347507cadefac5b64d30c9649ben_US
dc.identifier.urihttps://hdl.handle.net/2027.42/30754
dc.description.abstractThe effect of chromium, phosphorus, silicon and sulfur on the stress corrosion cracking of 304L stainless steel in CERT tests in high purity water or argon at 288[deg]C following irradiation with 3.4 MeV protons at 400[deg]C to 1 dpa, has been investigated using ultrahigh purity alloys (UHP) with controlled impurity additions. Grain boundary segregation of phosphorus or silicon due to proton irradiation was quantified using both Auger electron spectroscopy and scanning transmission electron microscopy, and the alloys with impurity element additions were observed to have greater grain boundary chromium depletion and nickel enrichment than the UHP alloy. The UHP alloy suffered severe cracking in CERT tests in water. Less cracking was found after CERT test of irradiated UHP+Por UHP+Si alloys, despite greater chromium depletion. This suggests a mitigating effect of phosphorus and silicon at grain boundaries. No cracking was found in argon tests, eliminating a purely mechanical embrittlement mechanism, but not eliminating a contribution from radiation hardening. Implanted hydrogen was not a factor in the intergranular cracking found.en_US
dc.format.extent1670277 bytes
dc.format.extent3118 bytes
dc.format.mimetypeapplication/pdf
dc.format.mimetypetext/plain
dc.language.isoen_US
dc.publisherElsevieren_US
dc.titleIrradiation assisted stress corrosion cracking of controlled purity 304L stainless steelsen_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.affiliationumDepartment of Nuclear Engineering The University of Michigan, Ann Arbor, MI 48109, USAen_US
dc.contributor.affiliationumDepartment of Nuclear Engineering The University of Michigan, Ann Arbor, MI 48109, USAen_US
dc.contributor.affiliationumDepartment of Nuclear Engineering The University of Michigan, Ann Arbor, MI 48109, USAen_US
dc.contributor.affiliationumDepartment of Nuclear Engineering The University of Michigan, Ann Arbor, MI 48109, USAen_US
dc.contributor.affiliationumDepartmennt of Nuclear Engineering and Department of Materials Science and Engineering, The University of Michigan, Ann Arbor, MI 48109, USAen_US
dc.description.bitstreamurlhttp://deepblue.lib.umich.edu/bitstream/2027.42/30754/1/0000404.pdfen_US
dc.identifier.doihttp://dx.doi.org/10.1016/0022-3115(93)90034-Ven_US
dc.identifier.sourceJournal of Nuclear Materialsen_US
dc.owningcollnameInterdisciplinary and Peer-Reviewed


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