Show simple item record

dc.contributor.authorMajumdar, S.
dc.contributor.authorKishor, J.
dc.contributor.authorBehera, A. N.
dc.contributor.authorVishwanadh, B.
dc.contributor.authorBorgohain, A.
dc.contributor.authorKapoor, R.
dc.contributor.authorTewari, R.
dc.contributor.authorKain, V.
dc.contributor.authorKrishnan, Madangopal
dc.contributor.authorDey, G. K.
dc.contributor.authorBanerjee, S.
dc.date.accessioned2022-02-05T21:51:44Z
dc.date.available2022-02-05T21:51:44Z
dc.date.copyright10/2/2020 12:00:00 AM
dc.date.issued2020
dc.identifier.issn2332-8983
dc.identifier.otherners_007_01_011603.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4276477
dc.description.abstractA novel process comprising of aluminothermic coreduction of mixed oxides followed by arc and electron beam melt refining was developed for preparation of Nb-1Zr-0.1C alloy. The parameters of the process were optimized by considering the thermodynamic (heat) and mass balance phenomenon. The ingots of the homogenized alloy produced after electron beam melt consolidation were further extruded into tubes. The alloy was vacuum annealed at 1350–1800 °C to study the stability of Nb2C and Nb(Zr)C carbide precipitates in the microstructure. Compression creep tests conducted at 900 and 1000 °C revealed a stress exponent value of 2 and activation energy of 508 kJ/mol. NbSi2-based coatings were developed on the Nb-1Zr-0.1C alloy tubes using pack siliconizing process. The coated alloy was tested for oxidation at 1250 °C, and corrosion in liquid lead-bismuth eutectic (LBE) alloy at 875 °C for prolonged duration. The silicide-coated alloy showed superior oxidation and LBE corrosion resistance at high temperatures. The alloy was found to be a promising material for coolant channels of high temperature reactors.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titlePreparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors
dc.typeJournal Paper
dc.journal.volume7
dc.journal.issue1
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4047919
dc.journal.fristpage011603-1
dc.journal.lastpage011603-14
dc.page14
dc.treeJournal of Nuclear Engineering and Radiation Science:;2020:;volume( 007 ):;issue: 001
dc.contenttypeFulltext


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record