Grain boundary engineering for control of tellurium diffusion in GH3535 alloy

被引:25
作者
Fu, Cai-Tao [1 ]
Wang Yinling [2 ]
Chu, Xiang-Wei [1 ]
Li Jiang [3 ]
Zhang, Wen-Zhu [4 ]
Qin Bai [4 ]
Shuang Xia [4 ]
Bin Leng [3 ]
Li, Zhi-Jun [3 ]
Ye, Xiang-Xi [3 ]
Fang Liu [1 ]
机构
[1] Univ Shanghai Sci & Technol, Sch Mat Sci & Engn, Shanghai 200093, Peoples R China
[2] Huanghuai Univ, Coll Mech & Energy Engn, Zhumadian 463000, Peoples R China
[3] Chinese Acad Sci, Shanghai Inst Appl Phys, Thorium Molten Salts Reactor Ctr, Shanghai 201800, Peoples R China
[4] Shanghai Univ, Sch Mat Sci & Engn, Shanghai 200072, Peoples R China
基金
中国国家自然科学基金;
关键词
Grain-clusters; Tellurium diffusion; EPMA; EBSD; Grain boundary engineering; GH3535; alloy; LOW-OXYGEN POTENTIALS; MOLTEN-SALT REACTOR; MO-CR SUPERALLOY; CARBIDE PRECIPITATION; SUPERCRITICAL WATER; OXIDATION BEHAVIOR; STAINLESS-STEEL; M6C CARBIDE; CORROSION; TEMPERATURE;
D O I
10.1016/j.jnucmat.2017.10.052
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The effect of grain boundary engineering (GBE) on the Te diffusion along the surface grain boundaries was investigated in GH3535 alloy. It can be found that GBE treatment increases obviously the fraction of low-Sigma coincidence site lattice (CSL) boundaries, especially the Sigma 3 ones, and introduces the large-size grain clusters. When the as-received (AR) and GBE-treated (GBET) specimens were exposed to Te vapor, only Sigma 3 boundaries were found to be resistant to Te diffusion. From the cross section and the surface, the fewer Te-attacked grain boundaries and the thinner corrosion layer can be observed in the GBET sample. The improvement of resistance to Te diffusion in the GBET sample can be attributed to the large size grain-clusters associated with high proportion of the Sigma 3(n) boundaries. (C) 2017 Elsevier B.V. All rights reserved.
引用
收藏
页码:76 / 83
页数:8
相关论文
共 42 条
  • [11] CORROSION BEHAVIOR OF STAINLESS-STEEL BY OXYGEN AND TELLURIUM AT LOW OXYGEN POTENTIALS
    FURUYA, H
    SAITO, M
    SUGISAKI, M
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1988, 154 (01) : 128 - 137
  • [12] Study of grain boundary character along intergranular stress corrosion crack paths in austenitic alloys
    Gertsman, VY
    Bruemmer, SM
    [J]. ACTA MATERIALIA, 2001, 49 (09) : 1589 - 1598
  • [13] TELLURIUM EMBRITTLEMENT OF TYPE-316 STEEL
    HEMSWORTH, JA
    NICHOLAS, MG
    CRISPIN, RM
    [J]. JOURNAL OF MATERIALS SCIENCE, 1990, 25 (12) : 5248 - 5256
  • [14] Towards the thorium fuel cycle with molten salt fast reactors
    Heuer, D.
    Merle-Lucotte, E.
    Allibert, M.
    Brovchenko, M.
    Ghetta, V.
    Rubiolo, P.
    [J]. ANNALS OF NUCLEAR ENERGY, 2014, 64 : 421 - 429
  • [15] Holcomb D. E., 2013, Report No. ORNL/TM-2013/401
  • [16] Improving the intergranular corrosion resistance of 304 stainless steel by grain boundary network control
    Hu, Changliang
    Xi, Shuang
    Li, Hui
    Liu, Tingguang
    Zhou, Bangxin
    Chen, Wenjue
    Wang, Ning
    [J]. CORROSION SCIENCE, 2011, 53 (05) : 1880 - 1886
  • [17] Compatibility of selected Ni-based alloys in molten Li,Na,Be/F salts with PuF3 and tellurium additions
    Ignatiev, Victor
    Surenkov, Aleksandr
    Gnidoi, Ivan
    Fedulov, Vladimir
    Uglov, Vadim
    Afonichkin, Valery
    Bovet, Andrei
    Subbotin, Vladimir
    Panov, Aleksandr
    Toropov, Andrei
    [J]. NUCLEAR TECHNOLOGY, 2008, 164 (01) : 130 - 142
  • [18] Alloys compatibility in molten salt fluorides: Kurchatov Institute related experience
    Ignatiev, Victor
    Surenkov, Alexandr
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2013, 441 (1-3) : 592 - 603
  • [19] Intergranular tellurium cracking of nickel-based alloys in molten Li, Be, Th, U/F salt mixture
    Ignatiev, Victor
    Surenkov, Alexander
    Gnidoy, Ivan
    Kulakov, Alexander
    Uglov, Vadim
    Vasiliev, Alexander
    Presniakov, Mikhail
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2013, 440 (1-3) : 243 - 249
  • [20] 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