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
  • [41] Assessment of a European V-4Cr-4Ti alloy - CEA-J57
    Le Flem, Marion
    Gentzbittel, Jean-Marie
    Wident, Pierre
    JOURNAL OF NUCLEAR MATERIALS, 2013, 442 (1-3) : S325 - S329
  • [42] Tensile and impact properties of V-4Cr-4Ti alloy heats 832665 and 832864
    Bray, TS
    Tsai, H
    Nowicki, LJ
    Billone, MC
    Smith, DL
    Johnson, WR
    Trester, PW
    JOURNAL OF NUCLEAR MATERIALS, 2000, 283 (PART I) : 633 - 636
  • [43] Performance of V-4Cr-4Ti alloy exposed to the JFT-2M tokamak environment
    Johnson, WR
    Trester, PW
    Sengoku, S
    Ishiyama, S
    Fukaya, K
    Eto, M
    Oda, T
    Hirohata, Y
    Hino, T
    Tsai, H
    JOURNAL OF NUCLEAR MATERIALS, 2000, 283 (PART I) : 622 - 627
  • [44] The microstructure of laser welded V-4Cr-4Ti alloy after ion irradiation
    Watanabe, H
    Nagamine, M
    Yamasaki, K
    Yoshida, N
    Heo, NJ
    Nagasaka, T
    Muroga, T
    PRICM 5: THE FIFTH PACIFIC RIM INTERNATIONAL CONFERENCE ON ADVANCED MATERIALS AND PROCESSING, PTS 1-5, 2005, 475-479 : 1491 - 1495
  • [45] The microstructure of laser welded V-4Cr-4Ti alloy after neutron irradiation
    Watanabe, H.
    Yamasaki, K.
    Higashizima, A.
    Yoshida, N.
    Nagasaka, T.
    Muroga, T.
    JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (SPEC. ISS.) : 794 - 799
  • [46] Deuterium retention in V-4Cr-4Ti alloy after deuterium ion irradiation
    Yamauchi, Y
    Yamada, T
    Hirohata, Y
    Hino, T
    Muroga, T
    JOURNAL OF NUCLEAR MATERIALS, 2004, 329 : 397 - 400
  • [47] Hydrogen embrittlement of a V4Cr4Ti alloy
    Chen, JM
    Xu, Y
    Qiu, SY
    Muroga, T
    Deng, Y
    Xu, ZY
    MATERIALS FOR ADVANCED ENERGY SYSTEMS AND FISSION AND FUSION ENGINEERING, PROCEEDINGS, 2003, : 421 - 428
  • [48] Effect on impact properties of adding tantalum to V-4Cr-4Ti ternary vanadium alloy
    Miyazawa, Takeshi
    Saito, Haruka
    Hishinuma, Yoshimitsu
    Nagasaka, Takuya
    Muroga, Takeo
    Shen, Jingjie
    Okuno, Yasuki
    Yu, Hao
    Kasada, Ryuta
    Hasegawa, Akira
    NUCLEAR MATERIALS AND ENERGY, 2022, 31
  • [49] Plasticity improvement and radiation hardening reduction of Y doped V-4Cr-4Ti alloy
    Zhang, Yifan
    Li, Ranran
    Diao, Sizhe
    Wan, Farong
    Zhan, Qian
    JOURNAL OF NUCLEAR MATERIALS, 2022, 560
  • [50] Verification of mechanical properties of a V-4CR-4TI alloy using finite element method
    Lee, CY
    Donahue, EG
    Odette, GR
    ADVANCES IN FRACTURE AND STRENGTH, PTS 1- 4, 2005, 297-300 : 1013 - 1018