On the interdiffusion in multilayered silicide coatings for the vanadium-based alloy V-4Cr-4Ti

被引:14
|
作者
Chaia, N. [1 ]
Portebois, L. [2 ]
Mathieu, S. [2 ]
David, N. [2 ]
Vilasi, M. [2 ]
机构
[1] Univ Sao Paulo, Escola Engn Lorena, Polo Urbo Ind Gleba AI 6, BR-12602810 Lorena, SP, Brazil
[2] Univ Lorraine, Inst Jean Lamour, UMR7198, Blvd Aiguillettes,BP70239, F-54506 Vandoeuvre Les Nancy, France
关键词
Coating; Transition metal suicides; Interdiffusion; Pack cementation; Vanadium alloys; GENERATION IV REACTORS; FUSION APPLICATIONS; OXIDATION; OXYGEN;
D O I
10.1016/j.jnucmat.2016.11.027
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
To provide protection against corrosion at high temperatures, suicide diffusion coatings were developed for the V-4Cr-4Ti alloy, which can be used as the fuel cladding in next-generation sodium-cooled fast breeder reactors. The multilayered cbatings were prepared by halide-activated pack cementation using MgF2 as the transport agent and pure silicon (high activity) as the master alloy. Coated pure vanadium and coated V-4Cr-4Ti alloy were studied and compared as substrates. In both cases, the growth of the suicide layers (V3Si, V5Si3, V6Si5 and VSi2) was controlled exclusively by solid-state diffusion, and the growth kinetics followed a parabolic law. Wagner's analysis was adopted to calculate the integrated diffusion coefficients for all suicides. The estimated values of the integrated diffusion coefficients range from approximately 10(-9) to 10(-13) cm(2) s(-1). Then, a diffusion-based numerical approach was used to evaluate the growth and consumption of the layers when the coated substrates were exposed at critical temperatures. The estimated lifetimes of the upper VSi2 layer were 400 h and 280 h for pure vanadium and the V-4Cr-4Ti alloy, respectively. The result from the numeric simulation was in good agreement with the layer thicknesses measured after aging the coated samples at 1150 degrees C under vacuum. (C) 2016 Elsevier B.V. All rights reserved.
引用
收藏
页码:148 / 156
页数:9
相关论文
共 50 条
  • [31] 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
  • [32] Stability and migration property of helium and self defects in vanadium and V-4Cr-4Ti alloy by first-principles
    Zhang, Pengbo
    Zhao, Jijun
    Qin, Ying
    Wen, Bin
    JOURNAL OF NUCLEAR MATERIALS, 2011, 413 (02) : 90 - 94
  • [33] Initial characterization of V-4Cr-4Ti and MHD coatings exposed to flowing Li
    Pint, B. A.
    Pawel, S. J.
    Howell, M.
    Moser, J. L.
    Garner, G. W.
    Santella, M. L.
    Tortorelli, P. F.
    Wiffen, F. W.
    DiStefano, J. R.
    JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 : 712 - 715
  • [34] Creep of V-4Cr-4Ti in a lithium environment
    Grossbeck, ML
    JOURNAL OF NUCLEAR MATERIALS, 2002, 307 (1 SUPPL.) : 615 - 619
  • [35] 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
  • [36] 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
  • [37] Correlation between hydrogen distribution in V-4Cr-4Ti alloy and impact strength
    Hatano, Y.
    Homma, H.
    Sakamura, T.
    Saitoh, H.
    Nagasaka, T.
    Muroga, T.
    Matsuyama, M.
    JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 : 569 - 571
  • [38] 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
  • [39] 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
  • [40] 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