Corrosion of 316L stainless steel in high temperature water and steam: effects of simultaneous proton irradiation

被引:1
|
作者
Hanbury, Rigel D. [1 ]
Was, Gary S. [2 ]
机构
[1] Bettis Atom Power Lab, 814 Pittsburgh McKeesport Blvd, West Mifflin, PA 15122 USA
[2] Univ Michigan, Nucl Engn & Radiol Sci, 2301 Bonisteel Blvd, Ann Arbor, MI 48109 USA
关键词
Stainless steel; STEM; Corrosion; Proton irradiation; PWR PRIMARY WATER; OXIDE-FILM; IN-SITU; RADIATION; DIFFUSION; OXIDATION; HYDROGEN; RELEASE; ALLOYS; DISSOLUTION;
D O I
10.1016/j.jnucmat.2024.155274
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
316L stainless steel was exposed to 320 degrees C hydrogenated water and 480 degrees C hydrogenated steam for 24 h and 72 h while simultaneously irradiated with 5.4 MeV protons to yield a damage rate of 7 x 10-7 dpa/s. Oxide films characterized in cross-section STEM revealed chemical and morphological differences. High levels of radiolysis in water resulted in significantly reduced corrosion rates while inducing dissolution of the inner oxide layer, whereas in steam the effects of radiolysis are insignificant. Conversely, displacement damage effects are negligible in water but significantly increase the corrosion rate in the steam condition through the growth of inner oxide porosity.
引用
收藏
页数:17
相关论文
共 50 条
  • [1] Corrosion of 316L stainless steel in high temperature water and steam: Mechanisms of corrosion
    Hanbury, Rigel D.
    Was, Gary S.
    JOURNAL OF NUCLEAR MATERIALS, 2024, 599
  • [2] Clarifying the mitigation effect of proton irradiation on the intergranular oxidation of 316L stainless steel in high temperature water
    Wang, Shengkai
    Zhang, Shihao
    Xie, Jiayu
    Feng, Xingyu
    Song, Miao
    Was, Gary S.
    Kuang, Wenjun
    ACTA MATERIALIA, 2022, 241
  • [3] Effect of pH on corrosion behavior of 316L stainless steel in hydrogenated high temperature water
    Wang, Jiazhen
    Wang, Jianqiu
    Ming, Hongliang
    Zhang, Zhiming
    Han, En-Hou
    MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION, 2018, 69 (05): : 580 - 589
  • [4] Oxide growth and dissolution on 316L stainless steel during irradiation in high temperature water
    Hanbury, Rigel D.
    Was, Gary S.
    CORROSION SCIENCE, 2019, 157 : 305 - 311
  • [5] Effects of irradiation temperature on tritium retention in stainless steel type 316L
    Matsuyama, Masao
    Zushi, Hideki
    Hanada, Kazuaki
    Oya, Yasuhisa
    Hatano, Yuji
    FUSION ENGINEERING AND DESIGN, 2021, 169
  • [6] Radiolysis driven changes to oxide stability during irradiation-corrosion of 316L stainless steel in high temperature water
    Raiman, Stephen S.
    Bartels, David M.
    Was, Gary S.
    JOURNAL OF NUCLEAR MATERIALS, 2017, 493 : 40 - 52
  • [7] Effects of chloride and oxygen on stress corrosion cracking of cold worked 316/316L austenitic stainless steel in high temperature water
    Du, Donghai
    Chen, Kai
    Lu, Hui
    Zhang, Lefu
    Shi, Xiuqiang
    Xu, Xuelian
    Andresen, Peter L.
    CORROSION SCIENCE, 2016, 110 : 134 - 142
  • [8] Effect of electropolishing on corrosion of nuclear grade 316L stainless steel in deaerated high temperature water
    Han, Yaolei
    Mei, Jinna
    Peng, Qunjia
    Han, En-Hou
    Ke, Wei
    CORROSION SCIENCE, 2016, 112 : 625 - 634
  • [9] High temperature deformation of 316L stainless steel
    Cabrera, ESP
    MATERIALS SCIENCE AND TECHNOLOGY, 2001, 17 (02) : 155 - 161
  • [10] Accelerated corrosion and oxide dissolution in 316L stainless steel irradiated in situ in high temperature water
    Raiman, Stephen S.
    Was, Gary S.
    JOURNAL OF NUCLEAR MATERIALS, 2017, 493 : 207 - 218