Grain growth and pore coarsening in dense nano-crystalline UO2+x fuel pellets

被引:27
作者
Yao, Tiankai [1 ]
Mo, Kun [2 ]
Yun, Di [2 ,3 ]
Nanda, Sonal [1 ]
Yacout, Abedellatif M. [2 ]
Lian, Jie [1 ]
机构
[1] Rensselaer Polytech Inst, Dept Mech Aerosp & Nucl Engn, Troy, NY 12180 USA
[2] Argonne Natl Lab, Nucl Engn Div, Lemont, IL USA
[3] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian, Shaanxi, Peoples R China
基金
美国国家科学基金会;
关键词
grain growth; pore; stoichiometry; UO2; URANIUM-DIOXIDE; SELF-DIFFUSION; DEFECT MECHANISM; OXYGEN; KINETICS;
D O I
10.1111/jace.14780
中图分类号
TQ174 [陶瓷工业]; TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
Dense nano-sized UO2+x pellets are synthesized by spark plasma sintering with controlled stoichiometries (UO2.03 and UO2.11) and grain sizes (similar to 100 nm), and subsequently isothermally annealed to study their effects on grain growth kinetics and microstructure stability. The grain growth kinetics is determined and analyzed focusing on the interaction between grain boundary migration, pore growth, and coalescence. Grains grow much bigger in nano-sized UO2.11 than UO2.03 upon thermal annealing, consistent with the fact that hyper-stoichiometric UO2+x is beneficial for sintering due to enhanced U ion diffusion from excessive O ion interstitials. The activation energies of the grain growth for UO2.03 and UO2.11 are determined as similar to 1.0 and similar to 2.0 eV, respectively. As compared with the micrometer-sized UO2 in which volumetric diffusion dominates the grain coarsening with an activation energy of similar to 3.0 eV, the enhanced grain growth kinetics in nano-sized UO2+x suggests that grain boundary diffusion controls grain growth. The higher activation energy of more hyper-stoichiometric nano-sized UO2.11 may be attributed to the excessive O interstitials pinning grain boundary migration.
引用
收藏
页码:2651 / 2658
页数:8
相关论文
共 31 条
  • [1] Phase field simulation of grain growth in porous uranium dioxide
    Ahmed, Karim
    Pakarinen, Janne
    Allen, Todd
    El-Azab, Anter
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2014, 446 (1-3) : 90 - 99
  • [2] ISOTHERMAL GRAIN-GROWTH KINETICS IN SINTERED UO2 PELLETS
    AINSCOUGH, JB
    OLDFIELD, BW
    WARE, JO
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1973, 49 (02) : 117 - 128
  • [3] GRAIN GROWTH IN PURE AND TITANIA-DOPED URANIUM DIOXIDE
    AMATO, I
    COLOMBO, RL
    BALZARI, AP
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1966, 18 (03) : 252 - &
  • [4] INFLUENCE OF STOICHIOMETRY ON THE RATE OF GRAIN GROWTH OF UO2
    AMATO, I
    COLOMBO, RL
    PROTTI, AM
    [J]. JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1963, 46 (08) : 407 - 407
  • [5] OXYGEN ION SELF-DIFFUSION IN URANIUM DIOXIDE
    AUSKERN, AB
    BELLE, J
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1961, 3 (03) : 267 - 276
  • [6] Grain growth in CeO2: Dopant effects, defect mechanism, and solute drag
    Chen, PL
    Chen, IW
    [J]. JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1996, 79 (07) : 1793 - 1800
  • [7] Grain boundary mobility in Y2O3: Defect mechanism and dopant effects
    Chen, PL
    Chen, IW
    [J]. JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1996, 79 (07) : 1801 - 1809
  • [8] Nuclear fuel in generation II and III reactors: research issues related to high burn-up
    Degueldre, C.
    Bertsch, J.
    Kuri, G.
    Martin, M.
    [J]. ENERGY & ENVIRONMENTAL SCIENCE, 2011, 4 (05) : 1651 - 1661
  • [9] Activation energy of UO2 and UO2+x sintering
    Dehaudt, P
    Bourgeois, L
    Chevrel, H
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2001, 299 (03) : 250 - 259
  • [10] Neutron Diffraction Study of the in Situ Oxidation of UO2
    Desgranges, Lionel
    Baldinozzi, Gianguido
    Rousseau, Gurvan
    Niepce, Jean-Claude
    Calvarin, Gilbert
    [J]. INORGANIC CHEMISTRY, 2009, 48 (16) : 7585 - 7592