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The Leaching Behavior of Unirradiated $UO_2$ Pellets in Wet Storage and Disposal Conditions

Park, Geun-Il   (Korea Atomic Energy Research InstituteCC0186830  ); Lee, Hoo-Kun   (Korea Atomic Energy Research InstituteCC0186830  );
  • 초록

    The leaching behavior of uranium from unirradiated CANDU UO $_2$ fuel pellet in the spent fuel wet storage and disposal conditions has been investigated. A modified IAEA leach test method was used, and then the extent of leaching was monitored by analysis for uranium in the leachant. The leach test has been performed in various leachants(demineralized water and boric acid solution at pH=6, synthetic granite groundwater) for a long-term period of 5.4 years, and the effect of temperature on the leach rate of uranium has been analyzed. The leach rates of uranium at $25^{\circ}C$ were dependent on the leachants. Over initial 100 days of leach periods, the leach rate in groundwater was the highest in three leachants and no significant differences of leach rates ore observed in the demineralized oater and boric acid solution. But these leach rates in three leachants around 2,000 days at $25^{\circ}C$ appeared to be reached the steady rates in the range of 1~5 $\times$ 10 $^{-8}$ g/ $\textrm{cm}^2$ day. The leach rate of uranium in groundwater shooed to be independent of the temperature, but those in both demineralized water and boric acid solution increased with temperature. These results show that the leaching behavior of uranium from UO $_2$ fuel in both the demineralized water ann boric acid may be controlled tv the surface oxidative.dissolution reaction of UO $_2$ and the leach rate of uranium in groundwater at room temperature could mainly be controlled by the complex reaction of dissolved uranyl ions with carbonate ions and no variation of leach rate of UO $_2$ in groundwater with temperature may be due to the local deposition of passivating uranyl phases on the surface.


  • 참고문헌 (24)

    1. Status Report on LWR Spent Fuel IAEA Leach Tests , Y. B. katayama;D. J. Bradley;C. O. Harvey , PNC-3173 / v.,pp.,
    2. Leaching and Irradiated UO₂Fuel , U. B. Eklund;r. S. forsyth , KBS-70 / v.,pp.,
    3. The dissolution of unirradiated UO₂fuel pellets , G. F. Thromas , AECl-TR-234 / v.,pp.,
    4. J. B. Hiskey , Symp. of Hydrogen Peroxide ASM Meeting / v.,pp.,
    5. Oxidation of UO₂in water containing oxygen , S. Aronson , Bettis Tech. Rev. WAPD-BT-10, Westinghouse Atomic Power Division Report,93 / v.,pp.,
    6. E. F. Westrum;F. Gronvold , J. Phys. Chem. Solids / v.23,pp.39,
    7. L. H. Johnson;D. W. Shoesmith;G. E. Lunashy;J. bailey;P. R. Tremaine , Nucl. Tech. / v.56,pp.238,
    8. The effect of precipiation on radionuclide release from used fuel , F. Garisto(et al.) , Proc. and Int. Conf. on Radioactive Waste manag. / v.,pp.,
    9. Elemental Release from Glass and Spent Fuel , G. L. McVay;D. J. Bradley;J. F. Kircher , ONWI-275 / v.,pp.,
    10. UO₂matrix dissolution rate and grain boundary inventories of Cs, Sr, Tc in spent LWR fuel , W. J. Gray;D. M. Strachan , Mat. Res. Soc. Symp. Proc. / v.212,pp.205,
    11. A Kinetics of the dissolution of uranium dioxide in carbonate-bicarbonate solutions , R. L. Pearson;M. E. Wadsworth , Proc. and UN Int'1. Conf. Peaceful Uses Atomic energy 3,333 / v.,pp.,
    12. The dissolution of irradiated UO₂fuel in groundwater , L. H. Johnson , AECl-6837 / v.,pp.,
    13. Crystallization of $U_3O_8$ and hydrated UO₃on UO₂fuel in aerated water near 200℃ , P. Taylor;D. D. Wood;D. G. Derrk;G. I. Park , J. of Nuclear Material / v.183,pp.105,
    14. Modelling of used-fuel dissolution , N. C. Garisto , AECL-TR-350 / v.,pp.,
    15. Spent LWR Fuel Leach Tests , Y. B. Katayama , PNL-2982 / v.,pp.,
    16. Leach test methodology for the waste/rock interaction technology program , D. J. Bradley;G. L. Mcray;D. G. Coles , PNL-3326 / v.,pp.,
    17. K. B. Harvy;C. D. Litke;C. A. Boase , Advances in Ceramics / v.8,pp.496,
    18. R. Wang;Y. B. Katayama , Nucl. Chem. Waste Manag. / v.3,pp.83,
    19. Dissolution mechanism of UO₂at various parametric conditions , K. Ollila , YJT-88-04 / v.,pp.,
    20. Anodic oxidation of UO₂-II. Electrochemical and X-ray photoelectrons spectroscopic studies in alkaline solution , S. Sunder;D. W. shoesmith;M. G. Bailey;G. J. wallase , J. of Electroanal. Chem. / v.151,pp.217,
    21. Studies of the dissolution mechanism of used fuel , L. H. Johnson , AECL-TR-350 / v.,pp.,
    22. The dissolution of unirradiated UO₂fuel pellet under simulated disposal conditions , G. F. Thomas;G. Till , Nucl. and Chem. Waste Manag. / v.5,pp.141,
    23. The dissolution of irradiated UO₂fuel under hydrothermal oxidizing conditions , L. H. Johnson;K. I. Burns;H. Joling;C. J. Moore , AECL-TR-128 / v.,pp.,
    24. The solubility of some phase in the system UO₃-Na₂O-H₂O in aqueous solutions at 60℃ and 90℃ , L. H. Brush , Dissertation, Harvard Univ. / v.,pp.,

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