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    Adhesion of Oxides Grown in Supercritical Water on Selected Austenitic and Ferritic/Martensitic Alloys

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 002::page 21006
    Author:
    Artymowicz, D.
    ,
    Bradley, C.
    ,
    Xing, B.
    ,
    Newman, R. C.
    DOI: 10.1115/1.4035331
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A series of austenitic alloys (800H, H214, I625, 310S, and 347) with different surface finishes were exposed to supercritical water (SCW) at 550 °C and 2.5 × 107 Pa for 120 h, 260 h, and 450 h in a static autoclave with an initial level of dissolved oxygen of 8 ppm. Indentation with a hardness indenter was used for assessment of oxide adhesion. This was compared with the results of a similar test on SCW-oxidized ferritic alloys. Delamination in all the tested ferritic alloys was insufficient for quantification of the results but allowed for qualitative comparison within this group. In the set of austenitic alloys, oxide on stainless steel (SS) 347 exfoliated during cooling from 550 °C, and from the remaining four alloys, only oxide on H214 delaminated, which made the qualitative comparison across the whole group impossible. Energy dispersive X-ray spectroscopy (EDX) revealed that under delaminated external Cr2O3 on H214 alloy, there was a submicron thick layer of Al-rich oxide. To investigate a possible oxide spallation on austenitic samples during exposure, mass loss obtained through descaling was compared with mass gain due to SCW exposure. The results indicated that the applied descaling procedure did not, in most cases, fully remove the scale. Apart from one case (SS 347 with alumina surface finish), there was no clear indication of oxide spallation.
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      Adhesion of Oxides Grown in Supercritical Water on Selected Austenitic and Ferritic/Martensitic Alloys

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    https://yetl.yabesh.ir/yetl1/handle/yetl/4235312
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorArtymowicz, D.
    contributor authorBradley, C.
    contributor authorXing, B.
    contributor authorNewman, R. C.
    date accessioned2017-11-25T07:18:40Z
    date available2017-11-25T07:18:40Z
    date copyright2017/1/3
    date issued2017
    identifier issn2332-8983
    identifier otherners_003_02_021006.pdf
    identifier urihttp://138.201.223.254:8080/yetl1/handle/yetl/4235312
    description abstractA series of austenitic alloys (800H, H214, I625, 310S, and 347) with different surface finishes were exposed to supercritical water (SCW) at 550 °C and 2.5 × 107 Pa for 120 h, 260 h, and 450 h in a static autoclave with an initial level of dissolved oxygen of 8 ppm. Indentation with a hardness indenter was used for assessment of oxide adhesion. This was compared with the results of a similar test on SCW-oxidized ferritic alloys. Delamination in all the tested ferritic alloys was insufficient for quantification of the results but allowed for qualitative comparison within this group. In the set of austenitic alloys, oxide on stainless steel (SS) 347 exfoliated during cooling from 550 °C, and from the remaining four alloys, only oxide on H214 delaminated, which made the qualitative comparison across the whole group impossible. Energy dispersive X-ray spectroscopy (EDX) revealed that under delaminated external Cr2O3 on H214 alloy, there was a submicron thick layer of Al-rich oxide. To investigate a possible oxide spallation on austenitic samples during exposure, mass loss obtained through descaling was compared with mass gain due to SCW exposure. The results indicated that the applied descaling procedure did not, in most cases, fully remove the scale. Apart from one case (SS 347 with alumina surface finish), there was no clear indication of oxide spallation.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleAdhesion of Oxides Grown in Supercritical Water on Selected Austenitic and Ferritic/Martensitic Alloys
    typeJournal Paper
    journal volume3
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4035331
    journal fristpage21006
    journal lastpage021006-8
    treeJournal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 002
    contenttypeFulltext
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