Initial oxidation behavior of forged 316lN stainless steel in simulated PWR primary water

Yueling Guo; En Hou Han; Jian Qiu Wang

doi:10.11903/1002.6495.2014.268

Initial oxidation behavior of forged 316lN stainless steel in simulated PWR primary water

Yueling Guo, En Hou Han^*, Jian Qiu Wang

^*Corresponding author for this work

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

Abstract

Forged 316LNSS has been selected as the main pipe line material used in the third generation nuclear power plants. The oxide scale formed on the forged 316LNSS after immersion in high temperature pressurized water with 2.3 mg/L of dissolved hydrogen (DH) was studied using scanning electron microscopy (SEM), X-ray diffraction (XRD) and X-ray photoelectron spectroscopy (XPS). Results showed that a double-layer oxide scale was grown on 316LNSS. The outer Ferich layer was composed of Fe₃O₄ and hydroxides (mainly Ni(OH)₂ and CrOOH) and the inner layer was composed of Cr-enriched spinel oxides. The mechanism of oxide scale formation was also discussed.

Original language	English
Pages (from-to)	313-320
Number of pages	8
Journal	Corrosion Science and Protection Technology
Volume	27
Issue number	4
DOIs	https://doi.org/10.11903/1002.6495.2014.268
Publication status	Published - Jul 2015
Externally published	Yes

Keywords

Corrosion
Forging
High temperature pressurized water
Nuclear material
Oxide film
Stainless steel

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10.11903/1002.6495.2014.268

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title = "Initial oxidation behavior of forged 316lN stainless steel in simulated PWR primary water",

abstract = "Forged 316LNSS has been selected as the main pipe line material used in the third generation nuclear power plants. The oxide scale formed on the forged 316LNSS after immersion in high temperature pressurized water with 2.3 mg/L of dissolved hydrogen (DH) was studied using scanning electron microscopy (SEM), X-ray diffraction (XRD) and X-ray photoelectron spectroscopy (XPS). Results showed that a double-layer oxide scale was grown on 316LNSS. The outer Ferich layer was composed of Fe3O4 and hydroxides (mainly Ni(OH)2 and CrOOH) and the inner layer was composed of Cr-enriched spinel oxides. The mechanism of oxide scale formation was also discussed.",

keywords = "Corrosion, Forging, High temperature pressurized water, Nuclear material, Oxide film, Stainless steel",

author = "Yueling Guo and Han, {En Hou} and Wang, {Jian Qiu}",

year = "2015",

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doi = "10.11903/1002.6495.2014.268",

language = "English",

volume = "27",

pages = "313--320",

journal = "Corrosion Science and Protection Technology",

issn = "1002-6495",

publisher = "Elsevier B.V.",

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TY - JOUR

T1 - Initial oxidation behavior of forged 316lN stainless steel in simulated PWR primary water

AU - Guo, Yueling

AU - Han, En Hou

AU - Wang, Jian Qiu

PY - 2015/7

Y1 - 2015/7

N2 - Forged 316LNSS has been selected as the main pipe line material used in the third generation nuclear power plants. The oxide scale formed on the forged 316LNSS after immersion in high temperature pressurized water with 2.3 mg/L of dissolved hydrogen (DH) was studied using scanning electron microscopy (SEM), X-ray diffraction (XRD) and X-ray photoelectron spectroscopy (XPS). Results showed that a double-layer oxide scale was grown on 316LNSS. The outer Ferich layer was composed of Fe3O4 and hydroxides (mainly Ni(OH)2 and CrOOH) and the inner layer was composed of Cr-enriched spinel oxides. The mechanism of oxide scale formation was also discussed.

AB - Forged 316LNSS has been selected as the main pipe line material used in the third generation nuclear power plants. The oxide scale formed on the forged 316LNSS after immersion in high temperature pressurized water with 2.3 mg/L of dissolved hydrogen (DH) was studied using scanning electron microscopy (SEM), X-ray diffraction (XRD) and X-ray photoelectron spectroscopy (XPS). Results showed that a double-layer oxide scale was grown on 316LNSS. The outer Ferich layer was composed of Fe3O4 and hydroxides (mainly Ni(OH)2 and CrOOH) and the inner layer was composed of Cr-enriched spinel oxides. The mechanism of oxide scale formation was also discussed.

KW - Corrosion

KW - Forging

KW - High temperature pressurized water

KW - Nuclear material

KW - Oxide film

KW - Stainless steel

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U2 - 10.11903/1002.6495.2014.268

DO - 10.11903/1002.6495.2014.268

M3 - Article

AN - SCOPUS:84944738207

SN - 1002-6495

VL - 27

SP - 313

EP - 320

JO - Corrosion Science and Protection Technology

JF - Corrosion Science and Protection Technology

IS - 4

ER -

Initial oxidation behavior of forged 316lN stainless steel in simulated PWR primary water

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