Corrosion behavior of stainless steel 316 in sub- and supercritical aqueous environments: Effect of LiOH additions

被引：29
|
作者：
Svishchev, Igor M. [1 ]
Carvajal-Ortiz, Ruth A. [1 ]
Choudhry, Kashif I. [1 ]
Guzonas, David A. [2 ]
机构：
[1] Trent Univ, Dept Chem, Peterborough, ON K9J 7B8, Canada
[2] Atom Energy Canada Ltd, Chalk River Labs, Chalk River, ON K0J 1J0, Canada
来源：
CORROSION SCIENCE | 2013年 / 72卷
基金：
加拿大自然科学与工程研究理事会;
关键词：
Stainless steel; Stripping voltammetry; High temperature corrosion; WATER-COOLED REACTOR; HIGH-TEMPERATURE; PITTING BEHAVIOR; HIGH-PRESSURE; OXIDE-FILMS; ALLOY; 625; CRACKING; CHEMISTRY; OXYGEN; IRON;
D O I：
10.1016/j.corsci.2013.02.005
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Corrosion control in nuclear power systems is examined via addition of LiOH to the coolant at pressurized water reactor (PWR) and supercritical water-cooled reactor (SCWR) operating conditions in stainless steel tubing. The loss of metal to the coolant is analyzed using the voltammetry method. The SEM/EDX analysis of metallographic cross-sections is performed. The results indicate that an adequate pH control is possible for water temperatures up to 500 degrees C. Above this temperature pH control becomes progressively more difficult as dielectric constant and density of water decrease. Significant hydrogen production is detected at 650 degrees C. (C) 2013 Elsevier Ltd. All rights reserved.
引用
收藏
页码：20 / 25
页数：6
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