Influence of temperature on the corrosion of uranium dioxide nuclear fuel

被引：0
|
作者：
Broczkowski, Michael E. [1 ]
Noel, Jamic J. [1 ]
Shoesmith, David W. [1 ]
机构：
[1] Univ Western Ontario, Dept Chem, 1151 Richmond St, London, ON N6A 5B7, Canada
来源：
SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXX | 2007年 / 985卷
关键词：
D O I：
暂无
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The anodic dissolution Of UO2 has been studied at 60 degrees C and the results compared to previous observations at 22 degrees C. The rate of oxidation/dissolution was determined electrochemically at constant potentials in the range -500 mV to 500 mV (vs. SCE). The composition of the electrochemically oxidized surface was determined by X-Ray Photoelectron Spectroscopy (XPS). The onset of oxidation (UO2 -> UO2+x) occurred at approximately the same potential (400 mV) at both temperatures. However, the conversion of U-V to U-VI, and hence to soluble UO22+, was accelerated by temperature. This acceleration of dissolution caused the development of acidity at localized sites on the fuel surface at lower (less oxidizing) potentials (>= 100 mV) at 60 degrees C than at 22 degrees C (>= 3,50 mV).
引用
收藏
页码：59 / +
页数：3
相关论文
共 50 条
  • [1] URANIUM DIOXIDE NUCLEAR FUEL
    PLACEK, C
    NORTH, ED
    INDUSTRIAL AND ENGINEERING CHEMISTRY, 1960, 52 (06): : 458 - 464
  • [2] Nuclear forensic analysis of uranium dioxide fuel pellets
    Spano, Tyler
    Corcoran, Loretta
    Simonetti, Antonio
    Dorais, Corinne
    Lewis, Stefanie
    Gunther, Timothy
    Burns, Peter
    ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, 2018, 255
  • [3] Thermodynamic treatment of uranium dioxide based nuclear fuel
    Thompson, W. T.
    Lewis, B. J.
    Corcoran, E. C.
    Kaye, M. H.
    White, S. J.
    Akbari, F.
    He, Z.
    Verrall, R.
    Higgs, J. D.
    Thompson, D. M.
    Besmann, T. M.
    Vogel, S. C.
    INTERNATIONAL JOURNAL OF MATERIALS RESEARCH, 2007, 98 (10) : 1004 - 1011
  • [4] P/M technology of uranium dioxide nuclear fuel
    Wu, Zhiming
    Fenmo Yejin Jishu/Powder Metallurgy Technology, 1996, 14 (01): : 63 - 68
  • [5] Colloids from the aqueous corrosion of uranium nuclear fuel
    Kaminski, MD
    Dimitrijevic, NM
    Mertz, CJ
    Goldberg, MM
    JOURNAL OF NUCLEAR MATERIALS, 2005, 347 (1-2) : 77 - 87
  • [6] Characterisation of corrosion products from degraded uranium dioxide fuel
    Woodall, Sean D.
    Hambley, Michelle
    Rawcliffe, John
    Willey, Dave
    Hambley, David
    JOURNAL OF NUCLEAR MATERIALS, 2021, 552
  • [7] Depleted uranium dioxide waste package for spent nuclear fuel
    Forsberg, CW
    Dole, LR
    SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXV, 2002, 713 : 143 - 150
  • [8] Conversion of Uranium Dioxide and Real Spent Nuclear Fuel into Nitrates
    Bondin, V. V.
    Bychkov, S. I.
    Revenko, Yu. A.
    Efremov, I. G.
    Murzin, A. A.
    Shadrin, A. Yu.
    Babain, V. A.
    Romanovskii, V. N.
    Kudryavtsev, E. G.
    RADIOCHEMISTRY, 2008, 50 (03) : 253 - 255
  • [9] A mixed-potential model to predict fuel (uranium dioxide) corrosion within a failed nuclear waste container
    Shoesmith, DW
    Kolar, M
    King, F
    CORROSION, 2003, 59 (09) : 802 - 816
  • [10] ON INFLUENCE OF RADIAL DEPRESSION OF HEAT GENERATION IN TEMPERATURE CALCULATIONS FOR CYLINDRICAL FUEL RODS CONSISTING OF METALLIC URANIUM URANIUM DIOXIDE AND URANIUM CARBIDE
    JOHANNSEN, K
    ATOMKERNENERGIE, 1966, 11 (7-8): : 270 - +
12345