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

被引：47
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.
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页数：12
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