Suppression of hydrogen absorption to V-4Cr-4Ti alloy by TiO2/TiC coating

被引:13
|
作者
Hirohata, Y
Motojima, D
Hino, T
Sengoku, S
机构
[1] Hokkaido Univ, Dept Nucl Engn, Kita Ku, Sapporo, Hokkaido 0608628, Japan
[2] Japan Atom Energy Res Inst, Naka Fus Res Estab, Tokai, Ibaraki 3191195, Japan
关键词
vanadium alloy; hydrogen absorption; titanium oxide; coating; embrittlement;
D O I
10.1016/S0022-3115(02)01418-6
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Titanium oxide film was coated on the surface of a V-4Cr-4Ti alloy to reduce hydrogen absorption at low temperature region. Titanium oxide was deposited by rf reactive magnetron sputtering with a titanium target using oxygen as sputter gas. The film consisted of a mixture of TiO2 and TiC. The content of TiO2 was approximately 80%. The atomic composition remained the same in the temperature range below 873 K. The film thickness also remained the same in the temperature region below 773 K. At the temperature higher than 973 K, the oxygen concentration decreased due to diffusion into the bulk of V-alloy, and the carbon concentration increased due to diffusion from the bulk of V-alloy. The hydrogen absorption rate of Ti-oxide coated V-alloy decreased with increase of the film thickness. In the case of the film with the thickness of 0.5 mum, the absorption rate was much smaller than that of non-coated V-alloy at the absorption temperature of 573 K. (C) 2003 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:172 / 176
页数:5
相关论文
共 50 条
  • [31] Pulse current electrodeposition of tungsten coatings on V-4Cr-4Ti alloy
    Jiang, Fan
    Zhang, Yingchun
    Li, Xuliang
    FUSION ENGINEERING AND DESIGN, 2015, 93 : 30 - 35
  • [32] Point defect behavior in electron irradiated V-4Cr-4Ti alloy
    Xu, Q
    Yoshiie, T
    Mori, H
    JOURNAL OF NUCLEAR MATERIALS, 2002, 307 : 886 - 890
  • [33] Retention and desorption behavior of helium in oxidized V-4Cr-4Ti alloy
    Oku, D.
    Yamada, T.
    Hirohata, Y.
    Yamauchi, Y.
    Hino, T.
    JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (SPEC. ISS.) : 864 - 868
  • [34] Effects of impurities on low activation characteristics of V-4Cr-4Ti alloy
    Wu, Y
    Muroga, T
    Huang, Q
    Chen, Y
    Nagasaka, T
    Sagara, A
    JOURNAL OF NUCLEAR MATERIALS, 2002, 307 (2 SUPPL.) : 1026 - 1030
  • [35] Influence of heat treatment on tritium distribution in V-4Cr-4Ti alloy
    Homma, H.
    Hatano, Y.
    Daifuku, H.
    Saitoh, H.
    Nagasaka, T.
    Muroga, T.
    Hara, M.
    Nakamura, Y.
    Matsuyama, M.
    JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (SPEC. ISS.) : 887 - 891
  • [36] Observation of tritium distribution in V-4Cr-4Ti alloy by tritium radioluminography
    Homma, H
    Saitoh, H
    Misawa, T
    Ohnishi, T
    MATERIALS TRANSACTIONS, 2002, 43 (03) : 451 - 454
  • [37] Effects of oxygen and oxidation on tensile behavior of V-4Cr-4Ti alloy
    Natesan, K
    Soppet, WK
    Uz, M
    JOURNAL OF NUCLEAR MATERIALS, 1998, 258 : 1476 - 1481
  • [38] Hydrogen absorption kinetics of V4Cr4Ti alloy prepared by aluminothermy
    Kumar, Sanjay
    Taxak, Manju
    Krishnamurthy, Nagaiyar
    INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, 2012, 37 (04) : 3283 - 3291
  • [39] Tungsten coating prepared on V-4Cr-4Ti alloy substrate by electrodeposition from molten salt in air atmosphere
    Jiang, Fan
    Zhang, Yingchun
    Li, Xuliang
    Sun, Ningbo
    Wang, Lili
    FUSION ENGINEERING AND DESIGN, 2014, 89 (02) : 83 - 87
  • [40] Creep of V-4Cr-4Ti in a lithium environment
    Grossbeck, ML
    JOURNAL OF NUCLEAR MATERIALS, 2002, 307 (1 SUPPL.) : 615 - 619