Influence of irradiation on stainless steel corrosion in PWR primary conditions

被引：2

作者：

Perrin, Stephane ^{[1
]}

Dumerval, Marie ^{[1
]}

Marchetti, Loic ^{[1
]}

Sennour, Mohamed ^{[2
]}

Jomard, Francois ^{[3
]}

Vaubaillon, Sylvain ^{[4
]}

Wouters, Yves ^{[5
]}

机构：

[1] CEA DEN DPC, SCCME, Saclay, France

[2] PSL Res Univ, MINES ParisTech, MAT Ctr Mat, Evry, France

[3] CNRS, Grp Etud Matiere Condensee, Versailles, France

[4] UEPTN, CEA, RHF, INSTN, Saclay, France

[5] Univ Grenoble, SIMaP, Grenoble, France

来源：

MINOS 2ND INTERNATIONAL WORKSHOP, IRRADIATION OF NUCLEAR MATERIALS: FLUX AND DOSE EFFECTS | 2016年 / 115卷

关键词：

MECHANISM;

D O I：

10.1051/epjconf/201611504006

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

引用

页数：24

共 4 条

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

Dumerval, Marie ;

Perrin, Stephane ;

Marchetti, Loic ;

Tabarant, Michel ;

Jomard, Francois ;

Wouters, Yves .

CORROSION SCIENCE, 2014, 85 :251-257

[2] Influence of Irradiation on the Oxide Film Formed on 316 L Stainless Steel in PWR Primary Water [J].

Perrin, Stephane ;

Marchetti, Loic ;

Duhamel, Cecilie ;

Sennour, Mohamed ;

Jomard, Francois .

OXIDATION OF METALS, 2013, 80 (5-6) :623-633

[3] The mechanism of oxide film formation on austenitic stainless steels in high temperature water [J].

Stellwag, B .

CORROSION SCIENCE, 1998, 40 (2-3) :337-370

[4] Corrosion Behavior of Stainless Steels in Simulated PWR Primary Water -Effect of Chromium Content in Alloys and Dissolved Hydrogen [J].

Terachi, Takumi ;

Yamada, Takuyo ;

Miyamoto, Tomoki ;

Arioka, Koji ;

Fukuyai, Koji .

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2008, 45 (10) :975-984

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