Corrosion behavior of 316L stainless steel in supercritical water environment

被引:7
|
作者
Yoon, JH [1 ]
Son, KS
Kim, HS
Mitton, B
Latanision, R
Yoo, YR
Kim, YS
机构
[1] Changwon Natl Univ, Dept Mat Sci & Engn, Chang Won, South Korea
[2] MIT, Dept Mat Sci & Engn, Cambridge, MA 02139 USA
[3] Andong Natl Univ, Sch Adv Mat Engn, Andong, South Korea
关键词
supercritical water oxidation (SCWO); high temperature corrosion; organic compound; 316L stainless steel; corrosion rate; corrosion mechanism;
D O I
10.4028/www.scientific.net/MSF.475-479.4207
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
There is a need to destroy both military and civilian hazardous waste and urgency, mandated by public concern over traditional waste handling methodologies, to safe and efficient alternative technologies. One very effective process for the destruction of such waste is supercritical water oxidation (SCWO). Nevertheless, corrosion of the materials of fabrication is a serious concern. This work intends to obtain the fundamental data for developing the corrosion resistant steel for the construction of SCWO system. The effects of various factors on the corrosion resistance of flat, welded, and U-bend 316L stainless steels in Trimsol solution were studied. Corroded product on surface was composed of multi-layer with oxides and salts, and dealloying was observed. Major corrosion phenomena of 316L stainless steel under SCWO condition were intergranular corrosion, pitting corrosion, SCC, and erosion corrosion. This work focused on the elucidation of corrosion mechanism of 316L stainless steel in SCWO environment.
引用
收藏
页码:4207 / 4210
页数:4
相关论文
共 50 条
  • [1] Specific Corrosion Behavior of 316L Stainless Steel in Mineral Water
    Capelle, J.
    Dmytrakh, I.
    Schwab, F.
    Pluvinage, G.
    [J]. MATERIALS SCIENCE, 2019, 54 (05) : 728 - 738
  • [2] Specific Corrosion Behavior of 316L Stainless Steel in Mineral Water
    J. Capelle
    I. Dmytrakh
    F. Schwab
    G. Pluvinage
    [J]. Materials Science, 2019, 54 : 728 - 738
  • [3] Stress corrosion cracking behavior of annealed and cold worked 316L stainless steel in supercritical water
    Saez-Maderuelo, A.
    Gomez-Briceno, A.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2016, 307 : 30 - 38
  • [4] Corrosion Behavior of 316L Stainless Steel and Alloy 625 in Supercritical Water Oxidation for Coking Wastewater Treatment
    Wang, Yuzhen
    Wang, Shuzhong
    Guo, Yang
    Xu, Donghai
    Tang, Xinying
    Yu, Guangxin
    Yu, Hang
    [J]. ENERGY ENGINEERING AND ENVIRONMENTAL ENGINEERING, PTS 1AND 2, 2013, 316-317 : 1037 - +
  • [5] A research on the corrosion and stress corrosion cracking susceptibility of 316L stainless steel exposed to supercritical water
    Guo, Xianglong
    Chen, Kai
    Gao, Wenhua
    Shen, Zhao
    Lai, Ping
    Zhang, Lefu
    [J]. CORROSION SCIENCE, 2017, 127 : 157 - 167
  • [6] EFFECT OF ELECTROLYTIC TREATMENT OF BALLAST WATER ON THE CORROSION BEHAVIOR OF 316L STAINLESS STEEL
    Liu Guangzhou
    Wang Jianming
    Zhang Jianqing
    Cao Chunan
    [J]. ACTA METALLURGICA SINICA, 2011, 47 (12) : 1600 - 1604
  • [7] Corrosion of 316 stainless steel in supercritical water
    Kim, H
    Kurata, Y
    Sanada, N
    [J]. PASSIVITY AND LOCALIZED CORROSION: AN INTERNATIONAL SYMPOSIUM IN HONOR OF PROFESSOR NORIO SATO, 1999, 99 (27): : 57 - 65
  • [8] Corrosion behavior of ion nitrided AISI 316L stainless steel
    Nosei, L.
    Farina, S.
    Avalos, M.
    Nachez, L.
    Gomez, B. J.
    Feugeas, J.
    [J]. THIN SOLID FILMS, 2008, 516 (06) : 1044 - 1050
  • [9] Influences of oxygen on corrosion characteristics of TiO2/316L stainless steel in supercritical water
    Wang, Yuzhen
    Liu, Zhuan
    Zhang, Xiaoqiang
    Gao, Fen
    Yang, Jianqiao
    Fang, Changqing
    Xu, Donghai
    Wang, Shuzhong
    [J]. INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, 2019, 44 (11) : 5099 - 5107
  • [10] Effect of thermal treatment on the corrosion resistance of Type 316L stainless steel exposed in supercritical water
    Jiao, Y.
    Zheng, W.
    Guzonas, D. A.
    Cook, W. G.
    Kish, J. R.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2015, 464 : 356 - 364