Corrosion of commercial alloys in FLiNaK molten salt containing EuF3 and simulant fission product additives

被引:26
作者
McAlpine, Samuel W. [1 ]
Skowronski, Natasha C. [1 ]
Zhou, Weiyue [1 ]
Zheng, Guiqiu [2 ]
Short, Michael P. [1 ]
机构
[1] MIT, Dept Nucl Sci & Engn, 77 Massachusetts Ave, Cambridge, MA 02139 USA
[2] MIT, Nucl Reactor Lab, 138 Albany St, Cambridge, MA 02139 USA
关键词
Molten salt; Tellurium; Hastelloy N; Incoloy; 800H; 316L stainless steel; Ni-201; FLiNaK; TELLURIUM CORROSION; DIFFUSION BEHAVIOR; MU-PHASE; TE; FLUORIDES; SYSTEMS;
D O I
10.1016/j.jnucmat.2020.151994
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
In liquid-fueled molten salt reactor designs, materials will be exposed to a molten salt containing a multitude of fission products and other corrosive species. Little work has been done to understand the unique corrosion characteristics of materials in fission product-laden liquid-fuel systems. In this study, we conducted corrosion experiments up to 150 h in duration which exposed four commercial alloys (Hastelloy N, Incoloy 800H, 316L stainless steel, and Ni-201) to three molten salt compositions in order to better understand corrosion in liquid-fuel systems and inform reactor design. It was found that the presence of simulant fission product species, at predicted concentrations, in a highly corrosive FLiNaK + EuF3 molten salt does not lead to any detectable increase in corrosion at reactor-relevant conditions. No penetration of simulant fission product species into the samples was detected. The unique corrosion morphology of each of the alloys tested in this work is discussed. In particular, Ni-201 was found to be an ideal salt-facing material in molten fluoride systems, and is essentially immune to corrosion. (C) 2020 Published by Elsevier B.V.
引用
收藏
页数:13
相关论文
共 46 条
  • [11] Structural and electronic properties of the μ-phase Fe-Mo compounds
    Cieslak, J.
    Przewoznik, J.
    Dubiel, S. M.
    [J]. JOURNAL OF ALLOYS AND COMPOUNDS, 2014, 612 : 465 - 470
  • [12] Corrosion of Incoloy 800H alloys with nickel cladding in FLiNaK salts at 850 °C
    Dai, Qilong
    Ye, Xiang-Xi
    Ai, Hua
    Chen, Shuangjian
    Jiang, Li
    Liang, Jianping
    Yu, Kun
    Leng, Bin
    Li, Zhijun
    Zhou, Xingtai
    [J]. CORROSION SCIENCE, 2018, 133 : 349 - 357
  • [13] Molten fluorides for nuclear applications
    Delpech, Sylvie
    Cabet, Celine
    Slima, Cyrine
    Picard, Gerard S.
    [J]. MATERIALS TODAY, 2010, 13 (12) : 34 - 41
  • [14] Grain boundary engineering for control of tellurium diffusion in GH3535 alloy
    Fu, Cai-Tao
    Wang Yinling
    Chu, Xiang-Wei
    Li Jiang
    Zhang, Wen-Zhu
    Qin Bai
    Shuang Xia
    Bin Leng
    Li, Zhi-Jun
    Ye, Xiang-Xi
    Fang Liu
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2017, 497 : 76 - 83
  • [15] Gehlbach R.E., 1968, INT S STRUCTURAL STA, P346, DOI [DOI 10.7449/1968/SUPERALLOYS_1968_346_366.PDF, 10.7449/1968/Superalloys_1968_346_366, DOI 10.7449/1968/SUPERALLOYS_1968_346_366]
  • [16] Goldschmidt H.J., 1967, Interstitial Alloys
  • [17] Measurement of europium (III)/europium (II) couple in fluoride molten salt for redox control in a molten salt reactor concept
    Guo, Shaoqiang
    Shay, Nikolas
    Wang, Yafei
    Zhou, Wentao
    Zhang, Jinsuo
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2017, 496 : 197 - 206
  • [18] Effect of Cr contents on the diffusion behavior of Te in Ni-based alloy
    Jia, Yanyan
    Li, Zhefu
    Ye, Xiangxi
    Liu, Renduo
    Leng, Bin
    Qiu, Jie
    Liu, Min
    Li, Zhijun
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2017, 497 : 101 - 106
  • [19] Effect of temperature on diffusion behavior of Te into nickel
    Jia, Yanyan
    Cheng, Hongwei
    Qiu, Jie
    Han, Fenfen
    Zou, Yang
    Li, Zhijun
    Zhou, Xingtai
    Xu, Hongjie
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2013, 441 (1-3) : 372 - 379
  • [20] Influence of grain size on tellurium corrosion behaviors of GH3535 alloy
    Jiang, Li
    Fu, Cai-Tao
    Leng, Bin
    Jia, Yan-yan
    Ye, Xiang-Xi
    Zhang, Wen-Zhu
    Bai, Qin
    Xia, Shuang
    Li, Zhi-Jun
    Liu, Fang
    Zhou, Xing-Tai
    [J]. CORROSION SCIENCE, 2019, 148 : 110 - 122