High-temperature creep properties of uranium dioxide pellet

被引:9
作者
Gao Jia-cheng [1 ]
Wang Liang-fen [1 ]
Wang Yong [1 ]
Wu Shu-fang [1 ]
机构
[1] Chongqing Univ, Coll Mat Sci & Engn, Chongqing 400044, Peoples R China
基金
中国国家自然科学基金;
关键词
uranium dioxide pellet; grain size; creep property; creep mechanism; DIFFUSION; MECHANISMS; BEHAVIOR;
D O I
10.1016/S1003-6326(09)60128-X
中图分类号
TF [冶金工业];
学科分类号
0806 ;
摘要
High-temperature creep properties of sintered uranium dioxide pellets with two grain sizes (9.0 mu m and 23.8 mu m) were studied. The results indicate that the creep rate becomes a little faster with the reduction of the uranium dioxide grain size at the same temperature and the same load. At the same temperature, the logarithmic value of the steady creep rate vs stress has linear relation, and with increasing load, the steady creep rate of the sintered uranium dioxide pellet increases. Under the same load, the steady creep rate of the sintered uranium dioxide pellet increases with increasing temperature; and the creep rates of sintered uranium dioxide pellet with the grain size of 9.0 mu m and 23.8 mu m under 10 MPa are almost the same. The creep process is controlled both by Nabarro-Herring creep and Hamper-Dorn creep for uranium dioxide pellet with grain size of 9.0 mu m, while Hamper-Dorn creep is the dominant mechanism for uranium dioxide with grain size of 23.8 mu m.
引用
收藏
页码:238 / 242
页数:5
相关论文
共 12 条
  • [1] The influence of temperature on the anodic oxidation/dissolution of uranium dioxide
    Broczkowski, M. E.
    Noel, J. J.
    Shoesmith, D. W.
    [J]. ELECTROCHIMICA ACTA, 2007, 52 (25) : 7386 - 7395
  • [2] Elevated temperature creep of polycrystalline uranium dioxide: from microscopic mechanisms to macroscopic behaviour
    Dherbey, F
    Louchet, F
    Mocellin, A
    Leclercq, S
    [J]. ACTA MATERIALIA, 2002, 50 (06) : 1495 - 1505
  • [3] A 2ND REPORT ON TILT BOUNDARIES IN HARD-SPHERE FCC CRYSTALS
    FROST, HJ
    SPAEPEN, F
    ASHBY, MF
    [J]. SCRIPTA METALLURGICA, 1982, 16 (10): : 1165 - 1170
  • [4] GAO Jia-cheng, 2007, J MATER SCI, V42, P33
  • [5] Simulation of diffusion of oxygen and uranium in uranium dioxide nanocrystals
    Kupryazhkin, A. Ya.
    Zhiganov, A. N.
    Risovany, D. V.
    Nekrassov, K. A.
    Risovany, V. D.
    Golovanov, V. N.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2008, 372 (2-3) : 233 - 238
  • [6] Chemical diffusion in uranium dioxide - influence of defect interactions
    Ruello, P
    Chirlesan, G
    Petot-Ervas, G
    Petot, C
    Desgranges, L
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2004, 325 (2-3) : 202 - 209
  • [7] CREEP-BEHAVIOR OF LOW-DENSITY URANIUM CARBIDE BASE ALLOYS
    SELTZER, MS
    WRIGHT, TR
    SPEIDEL, EO
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1975, 55 (03) : 327 - 334
  • [8] SOLOMON AA, 1995, MAT SCI ENG A-STRUCT, V191, P135
  • [9] A new interpretation of the mechanisms in Newtonian creep of uranium dioxides
    Wang, JN
    Nieh, TG
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1996, 228 (01) : 141 - 147
  • [10] YANG X, 2004, THESIS PENNSYLVANIA, P1