Effect of Tensile Stress on the Oxide Properties of a Nickel-Based Alloy 600 in Simulated PWR Secondary Water

被引：2

作者：

Bae, Byung-Joon ^{[1
,2
]}

Han, Jeoh ^{[1
]}

Hong, Jongsup ^{[2
]}

Hur, Do-Haeng ^{[1
]}

机构：

[1] Korea Atom Energy Res Inst, Mat Safety Technol Dev Div, Daejeon 34057, South Korea

[2] Yonsei Univ, Div Mech Engn, Seoul 03722, South Korea

来源：

MATERIALS | 2021年 / 14卷 / 21期

基金：

新加坡国家研究基金会;

关键词：

tensile stress; Alloy; 600; corrosion; oxide property; plastic deformation; electrochemical impedance; defect density; stress corrosion cracking; pressurized water reactor; CORROSION CRACKING BEHAVIOR; STEAM-GENERATOR TUBES; HIGH-TEMPERATURE; PASSIVE FILMS; STAINLESS-STEEL; QUANTITATIVE ASSESSMENT; ELECTRONIC-STRUCTURE; HEAT-TREATMENT; MECHANISM; DEGRADATION;

D O I：

10.3390/ma14216460

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：

The purpose of this work was to examine the effect of tensile stress on the oxide properties of a nickel-based Alloy 600 that was exposed to simulated nuclear steam generator water at 340 & DEG;C for 1000 h. The size of the outer oxide particles increased, and the chromium content of the inner oxides decreased under tensile stress. Electrochemical measurements revealed that the charge carrier density increased, and the charge transfer resistance and film resistance were reduced under the tensile stress condition. These changes in the oxide properties are attributed to the formation of short diffusion paths such as line and surface defects due to tensile deformation.

引用

页数：15

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