Characterisation of oxygen and hydrogen migration through oxide scales formed on nickel-base alloys in PWR primary medium conditions

被引：19

作者：

Jambon, Fanny ^{[1
]}

Marchetti, Loic ^{[1
]}

Jomard, Francois ^{[2
,3
]}

Chene, Jacques ^{[4
]}

机构：

[1] CEA, DEN, DPC, SCCME,Lab Etud Corros Aqueuse, F-91191 Gif Sur Yvette, France

[2] CNRS, Grp Etud Matiere Condensee, F-78035 Versailles, France

[3] Univ Versailles St Quentin, F-78035 Versailles, France

[4] CEA, CNRS, UMR 8587,DEN,DPC,SCCME, Lab Etud Corros Aqueuse,Equipe Hydrogene Mat Stru, F-91191 Gif Sur Yvette, France

来源：

SOLID STATE IONICS | 2013年 / 231卷

关键词：

Alloy; 600; Hydrogen; Oxygen; Diffusion; Isotope labelling; Stress corrosion cracking; HIGH-TEMPERATURE; OXIDATION; DIFFUSION; FILMS; BULK;

D O I：

10.1016/j.ssi.2012.10.012

中图分类号：

O64 [物理化学（理论化学）、化学物理学];

学科分类号：

070304 ; 081704 ;

摘要：

This study aims at providing quantitative data concerning the oxygen and hydrogen diffusion through the oxide scale formed on alloy 600 in PWR primary medium conditions (325 degrees C) using D-2 and O-18 isotopes as markers. The diffusion coefficients were calculated according to a short-circuit diffusion of the tracers along the oxide grain boundaries (so-called "C-regime"). The values obtained are respectively D-sc = 4.6+/-0.9 x 10(-17) cm(2)/s for O-18, and D-sc = 5.2 +/-1.2x 10(-17) cm(2)/s for D-2. These experiments confirm that the transport mechanism of hydrogen through the oxide scale as hydroxide ions on the anionic sublattice is highly probable. The effect of hydrogen subsequent absorption by the alloy substrate, notably in stress corrosion cracking phenomenon is discussed. (c) 2012 Published by Elsevier B.V.

引用

页码：69 / 73

页数：5

共 14 条

[1] A mechanism for the hydrogen uptake process in zirconium alloys [J].

Cox, B .

JOURNAL OF NUCLEAR MATERIALS, 1999, 264 (03) :283-294

[2]

Cox B., 1976, Advances in corrosion science and technology, V5, P173, DOI [10.1007/978-1-4615-9062-0_3, DOI 10.1007/978-1-4615-9062-0_3]

[3] Mechanism of hydrogen absorption during the exposure of alloy 600-like single-crystals to PWR primary simulated media [J].

Jambon, F. ;

Marchetti, L. ;

Jomard, F. ;

Chene, J. .

JOURNAL OF NUCLEAR MATERIALS, 2011, 414 (03) :386-392

[4]

Kroger F.A., 1956, Solid State Physics, V3, P273

[5] Photoelectrochemical study of nickel base alloys oxide films formed at high temperature and high pressure water [J].

Marchetti, L. ;

Perrin, S. ;

Wouters, Y. ;

Martin, F. ;

Pijolat, M. .

ELECTROCHIMICA ACTA, 2010, 55 (19) :5384-5392

[6] Corrosion mechanisms of Ni-base alloys in pressurized water reactor primary conditions [J].

Marchetti, Loic ;

Perrin, Stephane ;

Raquet, Olivier ;

Pijolat, M. .

HIGH TEMPERATURE CORROSION AND PROTECTION OF MATERIALS 7, PTS 1 AND 2, 2008, 595-598 :529-537

[7]

MISHIN YM, 1993, J PHYS III, V3, P863, DOI 10.1051/jp3:1993169

[8]

Morton D., 2001, NACE CORROSION 2001

[9] Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600 [J].

Panter, J ;

Viguier, B ;

Cloué, JM ;

Foucault, M ;

Combrade, P ;

Andrieu, E .

JOURNAL OF NUCLEAR MATERIALS, 2006, 348 (1-2) :213-221

[10] MEASUREMENTS OF SURFACE AND BULK PROPERTIES FOR THE INTERACTION OF HYDROGEN WITH INCONEL-600 [J].

ROTA, E ;

WAELBROECK, F ;

WIENHOLD, P ;

WINTER, J .

JOURNAL OF NUCLEAR MATERIALS, 1982, 111 (NOV-) :233-239

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