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    Performance of Aluminide and Cr-Modified Aluminide Pack Cementation-Coated Stainless Steel 304 in Supercritical Water at 700 °C

    Source: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 001::page 11014
    Author:
    Tepylo, Nick
    ,
    Huang, Xiao
    ,
    Jiang, Shengli
    ,
    Penttilä, Sami
    DOI: 10.1115/1.4040889
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The choice of materials is of great concern in the construction of Gen IV supercritical water reactors (SCWR), particularly the fuel cladding, due to the harsh environment of elevated temperatures and pressures. A material's performance under simulated conditions must be evaluated to support proper material selection by designers. In this study, aluminide and Cr-modified aluminide coated 304, as well as bare stainless steel 304 as a reference material, were tested in supercritical water (SCW) at 700 °C and 25 MPa for 1000 h. The results showed that all three samples experienced weight loss. However, the aluminide coated 304 had 20 to 40 times less weight loss compared to Cr-modified aluminide coated and bare stainless steel 304 specimens, respectively. Based on scanning electron microscope/energy dispersive X-ray spectroscopy (SEM/EDS) and X-ray diffraction (XRD) analysis results, spinel and hematite Fe2O3 formed on bare 304 after 1000 h in SCW while alumina was observed on both coated specimens, i.e., aluminide and Cr-modified aluminide surfaces. Oxide spallation was observed on the bare 304 and Cr-modified aluminide surface, contributing to a larger weight loss. Based on the results from this study, pure aluminide coating with Al content of 10–11 wt % demonstrated superior performance than bare 304 and Cr-modified aluminide coated 304.
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      Performance of Aluminide and Cr-Modified Aluminide Pack Cementation-Coated Stainless Steel 304 in Supercritical Water at 700 °C

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4255623
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    contributor authorTepylo, Nick
    contributor authorHuang, Xiao
    contributor authorJiang, Shengli
    contributor authorPenttilä, Sami
    date accessioned2019-03-17T09:41:31Z
    date available2019-03-17T09:41:31Z
    date copyright1/24/2019 12:00:00 AM
    date issued2019
    identifier issn2332-8983
    identifier otherners_005_01_011014.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4255623
    description abstractThe choice of materials is of great concern in the construction of Gen IV supercritical water reactors (SCWR), particularly the fuel cladding, due to the harsh environment of elevated temperatures and pressures. A material's performance under simulated conditions must be evaluated to support proper material selection by designers. In this study, aluminide and Cr-modified aluminide coated 304, as well as bare stainless steel 304 as a reference material, were tested in supercritical water (SCW) at 700 °C and 25 MPa for 1000 h. The results showed that all three samples experienced weight loss. However, the aluminide coated 304 had 20 to 40 times less weight loss compared to Cr-modified aluminide coated and bare stainless steel 304 specimens, respectively. Based on scanning electron microscope/energy dispersive X-ray spectroscopy (SEM/EDS) and X-ray diffraction (XRD) analysis results, spinel and hematite Fe2O3 formed on bare 304 after 1000 h in SCW while alumina was observed on both coated specimens, i.e., aluminide and Cr-modified aluminide surfaces. Oxide spallation was observed on the bare 304 and Cr-modified aluminide surface, contributing to a larger weight loss. Based on the results from this study, pure aluminide coating with Al content of 10–11 wt % demonstrated superior performance than bare 304 and Cr-modified aluminide coated 304.
    publisherThe American Society of Mechanical Engineers (ASME)
    titlePerformance of Aluminide and Cr-Modified Aluminide Pack Cementation-Coated Stainless Steel 304 in Supercritical Water at 700 °C
    typeJournal Paper
    journal volume5
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4040889
    journal fristpage11014
    journal lastpage011014-8
    treeJournal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 001
    contenttypeFulltext
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