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

Susan Bsat; Bingjie Xiao; Xiao Huang; Sami Penttilä

doi:10.1007/s11085-017-9784-7

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

Susan Bsat, Bingjie Xiao, Xiao Huang, Sami Penttilä

Carleton University

Research output: Contribution to journal › Article › Scientific › peer-review

18 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 language	English
Pages (from-to)	151-163
Number of pages	13
Journal	Oxidation of Metals
Volume	89
Issue number	1-2
Early online date	2017
DOIs	https://doi.org/10.1007/s11085-017-9784-7
Publication status	Published - 2018
MoE publication type	A1 Journal article-refereed

Keywords

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

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

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.",

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

author = "Susan Bsat and Bingjie Xiao and Xiao Huang and Sami Penttil{\"a}",

note = "Funding Information: Acknowledgements Funding to the Canada Gen IV National Program was provided by Natural Resources Canada through the Office of Energy Research and Development, Atomic Energy of Canada Limited and Natural Sciences and Engineering Research Council of Canada. Publisher Copyright: {\textcopyright} 2017, Springer Science+Business Media, LLC. Copyright: Copyright 2018 Elsevier B.V., All rights reserved.",

year = "2018",

doi = "10.1007/s11085-017-9784-7",

language = "English",

volume = "89",

pages = "151--163",

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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

N1 - Funding Information: Acknowledgements Funding to the Canada Gen IV National Program was provided by Natural Resources Canada through the Office of Energy Research and Development, Atomic Energy of Canada Limited and Natural Sciences and Engineering Research Council of Canada. Publisher Copyright: © 2017, Springer Science+Business Media, LLC. Copyright: Copyright 2018 Elsevier B.V., All rights reserved.

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.

KW - oxidation

KW - alloy 800H

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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U2 - 10.1007/s11085-017-9784-7

DO - 10.1007/s11085-017-9784-7

M3 - Article

SN - 0030-770X

VL - 89

SP - 151

EP - 163

JO - Oxidation of Metals

JF - Oxidation of Metals

IS - 1-2

ER -

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

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Keywords

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