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dc.contributor.authorGaudet
dc.contributor.authorMichel;McLellan
dc.contributor.authorAnne;Gerlich
dc.contributor.authorAdrian;Williams
dc.contributor.authorBruce
dc.date.accessioned2022-08-18T12:59:41Z
dc.date.available2022-08-18T12:59:41Z
dc.date.copyright5/17/2022 12:00:00 AM
dc.date.issued2022
dc.identifier.issn2332-8983
dc.identifier.otherners_008_03_031106.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4287231
dc.description.abstractZirconium alloys are well-positioned as the material of choice for nuclear in-core structures since they have a low neutron absorption cross section and possess good material properties under elevated neutron flux and high-temperature operating conditions. The Canadian supercritical water-cooled reactor (SCWR) concept pressure tube includes a transition from zirconium-tin alloy (Excel) to a yet to be selected stainless steel to allow it to be seal welded to the inlet plenum. Thus, a method to join zirconium and its alloys to ferrous and nickel-bearing alloys is desired. To this end, a series of experiments were carried out to demonstrate the feasibility of this method. A joint approaching the strength of the parent material was achieved using both rotary friction welding and co-extrusion methods, although the joints exhibited lower ductility than that of the parent material. Microstructural examination of the joint revealed a ∼200 nm to ∼1 μm intermetallic layer at the transition zone, which was the location of failure in the tensile specimen.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleJoining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components
dc.typeJournal Paper
dc.journal.volume8
dc.journal.issue3
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4054557
dc.journal.fristpage31106-1
dc.journal.lastpage31106-7
dc.page7
dc.treeJournal of Nuclear Engineering and Radiation Science:;2022:;volume( 008 ):;issue: 003
dc.contenttypeFulltext


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