Oxidation Behaviour of Alloys 800H, 3033 and 304 in High-Temperature Supercritical Water

Susan Bsat, Bingjie Xiao, Xiao Huang, Sami Penttilä

Research output: Contribution to journalArticleScientificpeer-review

5 Citations (Scopus)

Abstract

The choice of materials is of great concern in the construction of Gen IV supercritical water-cooled reactors (SCWRs), particularly the fuel cladding, due to the harsh environment of elevated temperatures and pressures. Material's performance under simulated conditions must be evaluated to support proper material selection by designers. In this study, alloys 800H, 3003 and 304 were tested in SCW at 700 °C and 25 MPa for 1000 h. The results showed that only alloy 3033 experienced weight gain while weight loss was found for alloys 304 and 800H. Based on SEM/EDS and XRD analyses, spinel and Cr2O3, in addition to small amount of Fe2O3, formed on 800H surface, while predominant Cr2O3 and some spinel were present on alloy 3033. Alloy 304 showed no evidence of Cr2O3 on the surface, although some Cr-containing spinel and Fe2O3 were detected on the surface.
Original languageEnglish
Pages (from-to)151-163
Number of pages13
JournalOxidation of Metals
Volume89
Issue number1-2
Early online date2017
DOIs
Publication statusPublished - 2018
MoE publication typeA1 Journal article-refereed

Fingerprint

Oxidation
Water
Temperature
Water cooled reactors
Energy dispersive spectroscopy
Scanning electron microscopy
spinell

Keywords

  • oxidation
  • alloy 800H
  • alloy 3033
  • alloy 304
  • supercritical water-cooled reactor (SCWR)
  • weight change
  • surface oxide
  • SEM
  • XRD

Cite this

Bsat, Susan ; Xiao, Bingjie ; Huang, Xiao ; Penttilä, Sami. / Oxidation Behaviour of Alloys 800H, 3033 and 304 in High-Temperature Supercritical Water. In: Oxidation of Metals. 2018 ; Vol. 89, No. 1-2. pp. 151-163.
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abstract = "The choice of materials is of great concern in the construction of Gen IV supercritical water-cooled reactors (SCWRs), particularly the fuel cladding, due to the harsh environment of elevated temperatures and pressures. Material's performance under simulated conditions must be evaluated to support proper material selection by designers. In this study, alloys 800H, 3003 and 304 were tested in SCW at 700 °C and 25 MPa for 1000 h. The results showed that only alloy 3033 experienced weight gain while weight loss was found for alloys 304 and 800H. Based on SEM/EDS and XRD analyses, spinel and Cr2O3, in addition to small amount of Fe2O3, formed on 800H surface, while predominant Cr2O3 and some spinel were present on alloy 3033. Alloy 304 showed no evidence of Cr2O3 on the surface, although some Cr-containing spinel and Fe2O3 were detected on the surface.",
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Oxidation Behaviour of Alloys 800H, 3033 and 304 in High-Temperature Supercritical Water. / Bsat, Susan; Xiao, Bingjie; Huang, Xiao; Penttilä, Sami.

In: Oxidation of Metals, Vol. 89, No. 1-2, 2018, p. 151-163.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Oxidation Behaviour of Alloys 800H, 3033 and 304 in High-Temperature Supercritical Water

AU - Bsat, Susan

AU - Xiao, Bingjie

AU - Huang, Xiao

AU - Penttilä, Sami

PY - 2018

Y1 - 2018

N2 - The choice of materials is of great concern in the construction of Gen IV supercritical water-cooled reactors (SCWRs), particularly the fuel cladding, due to the harsh environment of elevated temperatures and pressures. Material's performance under simulated conditions must be evaluated to support proper material selection by designers. In this study, alloys 800H, 3003 and 304 were tested in SCW at 700 °C and 25 MPa for 1000 h. The results showed that only alloy 3033 experienced weight gain while weight loss was found for alloys 304 and 800H. Based on SEM/EDS and XRD analyses, spinel and Cr2O3, in addition to small amount of Fe2O3, formed on 800H surface, while predominant Cr2O3 and some spinel were present on alloy 3033. Alloy 304 showed no evidence of Cr2O3 on the surface, although some Cr-containing spinel and Fe2O3 were detected on the surface.

AB - The choice of materials is of great concern in the construction of Gen IV supercritical water-cooled reactors (SCWRs), particularly the fuel cladding, due to the harsh environment of elevated temperatures and pressures. Material's performance under simulated conditions must be evaluated to support proper material selection by designers. In this study, alloys 800H, 3003 and 304 were tested in SCW at 700 °C and 25 MPa for 1000 h. The results showed that only alloy 3033 experienced weight gain while weight loss was found for alloys 304 and 800H. Based on SEM/EDS and XRD analyses, spinel and Cr2O3, in addition to small amount of Fe2O3, formed on 800H surface, while predominant Cr2O3 and some spinel were present on alloy 3033. Alloy 304 showed no evidence of Cr2O3 on the surface, although some Cr-containing spinel and Fe2O3 were detected on the surface.

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KW - alloy 3033

KW - alloy 304

KW - supercritical water-cooled reactor (SCWR)

KW - weight change

KW - surface oxide

KW - SEM

KW - XRD

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