Hydrogen absorption associated with the corrosion mechanism of 316L stainless steels in primary medium of Pressurized Water Reactor (PWR)

被引:30
作者
Dumerval, Marie [1 ,5 ]
Perrin, Stephane [1 ]
Marchetti, Loic [2 ]
Tabarant, Michel [3 ]
Jomard, Francois [4 ]
Wouters, Yves [5 ]
机构
[1] CEA, DEN, DPC, Lab Etud Corros Aqueuse,SCCME, F-91191 Gif Sur Yvette, France
[2] CEA, DEN, DTCD,SECM, Lab Etud Comportement Long Terme Mat Conditioninn, F-30207 Bagnols Sur Ceze, France
[3] CEA, DEN, DPC, Lab Ingn Surfaces & Lasers,SEARS, F-91191 Gif Sur Yvette, France
[4] CNRS, Grp Etud MAtiere Condensee, F-78035 Versailles, France
[5] Univ Grenoble, SIMaP, F-38402 St Martin Dheres, France
关键词
Stainless steel; SIMS; Oxidation; Reactor conditions; Hydrogen absorption; OXIDE-FILM; OXIDATION EXPERIMENTS; DEUTERIUM; CRACKING; KINETICS; ALLOYS;
D O I
10.1016/j.corsci.2014.04.025
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Samples of 316L were exposed at 325 degrees C to PWR primary water labelled with deuterium and oxygen 18. The SIMS and GD-OES analysis has revealed the presence of deuterium in the internal oxide layer and in the underlying alloy. Two-stage corrosion experiments have shown that the oxygen and hydrogen transport in the oxide layer is not coupled and that the short-circuit diffusion coefficient of O-18 in the oxide scale: D-sc = (9 +/- 1).10(-17) cm(2) s(-1). These results are used to propose a mechanism describing the anionic growth of the protective oxide layer and the concomitant adsorption of hydrogen in the alloy. (C) 2014 Elsevier Ltd. All rights reserved.
引用
收藏
页码:251 / 257
页数:7
相关论文
共 27 条
[1]   MODELING OF O-18 TRACER DISTRIBUTION DURING DOUBLE OXIDATION EXPERIMENTS FOR INWARD GROWING SCALES [J].
APPANNAGAARI, N ;
BASU, SN .
JOURNAL OF APPLIED PHYSICS, 1995, 78 (03) :2060-2069
[2]   Composition, structure and properties of the oxide films formed on the stainless steel 316L in a primary type PWR environment [J].
Belo, MD ;
Walls, M ;
Hakiki, NE ;
Corset, J ;
Picquenard, E ;
Sagon, G ;
Noel, D .
CORROSION SCIENCE, 1998, 40 (2-3) :447-463
[3]  
Bisor-Melloul C., 2010, THESIS, P260
[4]   Effect of surface preparation on the corrosion of austenitic stainless steel 304L in high temperature steam and simulated PWR primary water [J].
Cisse, Sarata ;
Laffont, Lydia ;
Tanguy, Benoit ;
Lafont, Marie-Christine ;
Andrieu, Eric .
CORROSION SCIENCE, 2012, 56 :209-216
[5]  
Dieudonne T., 2012, THESIS, P272
[6]   Effects of dissolved hydrogen and strain rate on IASCC behavior in highly irradiated stainless steels [J].
Fukuya, Koji ;
Nishioka, Hiromasa ;
Fujii, Katsuhiko ;
Torimaru, Tadahiko .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2008, 45 (05) :452-458
[7]   Stress corrosion cracking on irradiated 316 stainless steel [J].
Furutani, G ;
Nakajima, N ;
Konishi, T ;
Kodama, M .
JOURNAL OF NUCLEAR MATERIALS, 2001, 288 (2-3) :179-186
[8]   Measurement of deuterium and helium by glow-discharge optical emission spectroscopy for plasma-surface interaction studies [J].
Hatano, Yuji ;
Shi, Jie ;
Yoshida, Naoaki ;
Futagami, Naoki ;
Oya, Yasuhisa ;
Nakamura, Hirofumi .
FUSION ENGINEERING AND DESIGN, 2012, 87 (7-8) :1091-1094
[9]   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
[10]   Characterisation of oxygen and hydrogen migration through oxide scales formed on nickel-base alloys in PWR primary medium conditions [J].
Jambon, Fanny ;
Marchetti, Loic ;
Jomard, Francois ;
Chene, Jacques .
SOLID STATE IONICS, 2013, 231 :69-73