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    Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 007 ):;issue: 001::page 011603-1
    Author:
    Majumdar, S.
    ,
    Kishor, J.
    ,
    Behera, A. N.
    ,
    Vishwanadh, B.
    ,
    Borgohain, A.
    ,
    Kapoor, R.
    ,
    Tewari, R.
    ,
    Kain, V.
    ,
    Krishnan, Madangopal
    ,
    Dey, G. K.
    ,
    Banerjee, S.
    DOI: 10.1115/1.4047919
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A 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.
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      Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4276477
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorMajumdar, S.
    contributor authorKishor, J.
    contributor authorBehera, A. N.
    contributor authorVishwanadh, B.
    contributor authorBorgohain, A.
    contributor authorKapoor, R.
    contributor authorTewari, R.
    contributor authorKain, V.
    contributor authorKrishnan, Madangopal
    contributor authorDey, G. K.
    contributor authorBanerjee, S.
    date accessioned2022-02-05T21:51:44Z
    date available2022-02-05T21:51:44Z
    date copyright10/2/2020 12:00:00 AM
    date issued2020
    identifier issn2332-8983
    identifier otherners_007_01_011603.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4276477
    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.
    publisherThe American Society of Mechanical Engineers (ASME)
    titlePreparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors
    typeJournal Paper
    journal volume7
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4047919
    journal fristpage011603-1
    journal lastpage011603-14
    page14
    treeJournal of Nuclear Engineering and Radiation Science:;2020:;volume( 007 ):;issue: 001
    contenttypeFulltext
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