DC Field | Value | Language |
---|---|---|
dc.contributor.author | CHOO, KN | ko |
dc.contributor.author | KANG, YH | ko |
dc.contributor.author | Pyun, Su Il | ko |
dc.contributor.author | URBANIC, VF | ko |
dc.date.accessioned | 2013-02-24T11:16:00Z | - |
dc.date.available | 2013-02-24T11:16:00Z | - |
dc.date.created | 2012-02-06 | - |
dc.date.created | 2012-02-06 | - |
dc.date.issued | 1994-05 | - |
dc.identifier.citation | JOURNAL OF NUCLEAR MATERIALS, v.209, no.3, pp.226 - 235 | - |
dc.identifier.issn | 0022-3115 | - |
dc.identifier.uri | http://hdl.handle.net/10203/56753 | - |
dc.description.abstract | The 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.language | English | - |
dc.publisher | ELSEVIER SCIENCE BV | - |
dc.title | EFFECT OF COMPOSITION AND HEAT-TREATMENT ON THE MICROSTRUCTURE AND CORROSION BEHAVIOR OF ZR-NB ALLOYS | - |
dc.type | Article | - |
dc.identifier.wosid | A1994NL81300003 | - |
dc.type.rims | ART | - |
dc.citation.volume | 209 | - |
dc.citation.issue | 3 | - |
dc.citation.beginningpage | 226 | - |
dc.citation.endingpage | 235 | - |
dc.citation.publicationname | JOURNAL OF NUCLEAR MATERIALS | - |
dc.identifier.doi | 10.1016/0022-3115(94)90256-9 | - |
dc.contributor.nonIdAuthor | CHOO, KN | - |
dc.contributor.nonIdAuthor | KANG, YH | - |
dc.contributor.nonIdAuthor | URBANIC, VF | - |
dc.type.journalArticle | Article | - |
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