Role of irradiation and irradiation defects on the oxidation first stages of a 316L austenitic stainless steel

被引：43
|
作者：
Boisson, M. [1 ,2 ]
Legras, L. [2 ]
Andrieu, E. [1 ]
Laffont, L. [1 ]
机构：
[1] Univ Toulouse, CNRS, ENSIACET, CIRIMAT, 4 Allee Emile Monso,BP 44362, F-31030 Toulouse 4, France
[2] EDF R&D, EDF Lab Renardieres MMC, Ave Renardieres Ecuelles, F-77818 Moret Sur Loing, France
来源：
CORROSION SCIENCE | 2019年 / 161卷
关键词：
Stainless steel; TEM; STEM; Oxidation; RADIATION-INDUCED SEGREGATION; PWR PRIMARY WATER; CRACK INITIATION BEHAVIOR; HIGH-TEMPERATURE; CORROSION BEHAVIOR; OXIDE-FILM; MICROSTRUCTURAL EVOLUTION; DEFORMATION; MECHANISM; REACTOR;
D O I：
10.1016/j.corsci.2019.108194
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The role of irradiation and irradiation defects on the oxidation first stages of 316 L alloy was investigated. A sample with both a proton pre-irradiated and an unirradiated area was exposed to a simulated PWR environment during 24 hours. Irradiation defects and Radiation Induced Segregation at grain boundary and on irradiation defects were characterized and quantified and their effect on the oxidation was evaluated. Irradiation affects the morphology, thickness and chemistry of the oxide layers formed. It enhances the oxidation kinetic and induces the formation of an inner oxide richer in chromium. Defects induced by irradiation act as preferential nucleation sites.
引用
收藏
页数：12
相关论文
共 50 条
  • [1] Precipitation stages in a 316L austenitic stainless steel
    Wasnik, DN
    Dey, GK
    Kain, V
    Samajdar, I
    SCRIPTA MATERIALIA, 2003, 49 (02) : 135 - 141
  • [2] Irradiation testing of 316L(N)-IG austenitic stainless steel for ITER
    van Osch, E.V.
    Horsten, M.G.
    de Vries, M.I.
    Journal of Nuclear Materials, 1998, 258-263 (pt A): : 301 - 307
  • [3] Irradiation testing of 316L(N)-IG austenitic stainless steel for ITER
    van Osch, EV
    Horsten, MG
    de Vries, MI
    JOURNAL OF NUCLEAR MATERIALS, 1998, 258 : 301 - 307
  • [4] Hydrogen Trapping by Irradiation-Induced Defects in 316L Stainless Steel
    Bach, Anne-Cecile
    Martin, Frantz
    Duhamel, Cecilie
    Perrin, Stephane
    Jomard, Francois
    Crepin, Jerome
    PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, 2018, : 919 - 935
  • [5] Helium irradiation-induced defects in deformed 316L stainless steel
    Gong, Yihao
    Jin, Shuoxue
    Lu, Eryang
    Kuang, Peng
    Zhu, Te
    Cao, Xingzhong
    Guo, Liping
    Wang, Baoyi
    PHILOSOPHICAL MAGAZINE, 2018, 98 (02) : 95 - 106
  • [6] Tritium decay, irradiation and hydrogenihelium effects on type 316L austenitic stainless steel
    Louthan, MR
    HYDROGEN EFFECTS ON MATERIAL BEHAVIOR AND CORROSION DEFORMATION INTERACTIONS, 2003, : 1029 - 1038
  • [7] Irradiation resistance of a nanostructured 316 austenitic stainless steel
    Rajan, P. B. Revathy
    Monnet, I.
    Hug, E.
    Etienne, A.
    Enikeev, N.
    Keller, C.
    Sauvage, X.
    Valiev, R.
    Radiguet, B.
    6TH INTERNATIONAL CONFERENCE ON NANOMATERIALS BY SEVERE PLASTIC DEFORMATION (NANOSPD6), 2014, 63
  • [8] Irradiation behavior of nanostructured 316 austenitic stainless steel
    B. Radiguet
    A. Etienne
    P. Pareige
    X. Sauvage
    R. Valiev
    Journal of Materials Science, 2008, 43 : 7338 - 7343
  • [9] Irradiation behavior of nanostructured 316 austenitic stainless steel
    Radiguet, B.
    Etienne, A.
    Pareige, P.
    Sauvage, X.
    Valiev, R.
    JOURNAL OF MATERIALS SCIENCE, 2008, 43 (23-24) : 7338 - 7343
  • [10] Effects of irradiation temperature on tritium retention in stainless steel type 316L
    Matsuyama, Masao
    Zushi, Hideki
    Hanada, Kazuaki
    Oya, Yasuhisa
    Hatano, Yuji
    FUSION ENGINEERING AND DESIGN, 2021, 169
12345