EFFECT OF COMPOSITION AND HEAT-TREATMENT ON THE MICROSTRUCTURE AND CORROSION BEHAVIOR OF ZR-NB ALLOYS

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dc.contributor.authorCHOO, KNko
dc.contributor.authorKANG, YHko
dc.contributor.authorPyun, Su Ilko
dc.contributor.authorURBANIC, VFko
dc.date.accessioned2013-02-24T11:16:00Z-
dc.date.available2013-02-24T11:16:00Z-
dc.date.created2012-02-06-
dc.date.created2012-02-06-
dc.date.issued1994-05-
dc.identifier.citationJOURNAL OF NUCLEAR MATERIALS, v.209, no.3, pp.226 - 235-
dc.identifier.issn0022-3115-
dc.identifier.urihttp://hdl.handle.net/10203/56753-
dc.description.abstractThe influence of Nb content and heat treatment on the structure and isothermal corrosion behavior of Zr-Nb alloys at 300, 360 and 400-degrees-C in static heavy water and steam (1500 psi) are presented. The formation of the martensitic alpha'-phase by beta-quenching treatment results in high weight gains at all test temperatures. Up to 5 wt% Nb, the corrosion resistance of the quenched alloy decreases linearly with increasing Nb content. Through ageing of the beta-quenched specimens, Nb-rich beta-Nb particles are precipitated in the matrix, at twin and alpha'-needle boundaries. The corrosion resistance is greatly improved due to the reduction in Nb supersaturation. The agglomerated large beta-Nb precipitates have detrimental effects on the corrosion resistance as compared to fine precipitates. The corrosion rates of the specimens containing the beta-Zr phase are affected by the Nb content in the beta-Zr phase and seem to show similar weight gains irrespective of the amount of beta-Zr if they form a continuous beta-Zr network. Under the neutron irradiation the corrosion resistance of quenched specimens was sharply improved, but neutron flux had little or no effect on the aged ones.-
dc.languageEnglish-
dc.publisherELSEVIER SCIENCE BV-
dc.titleEFFECT OF COMPOSITION AND HEAT-TREATMENT ON THE MICROSTRUCTURE AND CORROSION BEHAVIOR OF ZR-NB ALLOYS-
dc.typeArticle-
dc.identifier.wosidA1994NL81300003-
dc.type.rimsART-
dc.citation.volume209-
dc.citation.issue3-
dc.citation.beginningpage226-
dc.citation.endingpage235-
dc.citation.publicationnameJOURNAL OF NUCLEAR MATERIALS-
dc.identifier.doi10.1016/0022-3115(94)90256-9-
dc.contributor.nonIdAuthorCHOO, KN-
dc.contributor.nonIdAuthorKANG, YH-
dc.contributor.nonIdAuthorURBANIC, VF-
dc.type.journalArticleArticle-
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