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Technical Paper

Fission Product Release from Spent UO2 Fuel Under Uranium-Saturated Oxic Conditions

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Pages 204-213 | Published online: 12 May 2017

References

  • U. B. EKLUND and R. S. FORSYTH, Technical Report 70, Swedish Nuclear Fuel and Waste Management Company (1978).
  • R. S. FORSYTH, Ed., “Fuel Rod D07/B15 from Ringhals 2 PWR: Source Material for Corrosion/Leach Tests in Groundwater—Fuel Rod/Pellet Characterization Program Part One,” Technical Report 87-02, Swedish Nuclear Fuel and Waste Management Company (1987).
  • R. S. FORSYTH, L. O. WERME, and J. BRUNO, “The Corrosion of Spent Uranium Dioxide Fuel in Synthetic Groundwater,” J. Nucl. Mater., 138, 1 (1986).
  • R. S. FORSYTH and L. O. WERME, “Corrosion Tests on Spent PWR Fuel in Synthetic Groundwater,” Technical Report 87-16, Swedish Nuclear Fuel and Waste Management Company (1987).
  • R. FORSYTH, K. SVANBERG, and L. O. WERME, “The Corrosion of Spent UO2 Fuel in Synthetic Groundwater,” Mater. Res. Soc. Symp. Proc., 26, 179 (1984).
  • R. S. FORSYTH and L. O. WERME, “The Corrosion of Spent UO2 Fuel in Synthetic Groundwater,” Mater. Res. Soc. Symp. Proc., 50, 327 (1985).
  • S. SUNDER, D. W. SHOESMITH, M. G. BAILEY, F. W. STANCHELL, and N. S. McINTYRE, “Anodic Oxidation of UO2. Part I. Electrochemical and X-Ray Photoelectron Spectroscopic Studies in Neutral Solutions,” J. Electroanal. Chem., 130, 163 (1981).
  • H. MATZKE, European Institute of Transuranic Elements, Personal Communication (1988).
  • I. J. HASTINGS, E. MIZZAN, A. M. ROSS, J. R. KELM, R. J. CHENIER, and D. H. ROSE, “Postirradiation Behavior of UO2 Fuel II: Fragments at 175 to 275°C in Air,” Nucl. Technol., 68, 40 (1985).
  • R. E. WOODLEY, R. E. EINZIGER, and H. C. BUCHANAN, “Measurement of the Oxidation of Spent Fuel Between 140 and 225°C by Thermogravimetric Analysis,” WHC-EP-0107, Westinghouse Hanford Company (1988).
  • R. E. EINZIGER and R. E. WOODLEY, “Low Temperature Spent Fuel Oxidation Under Tuff Repository Conditions,” HEDL-SA-3271FP, Westinghouse Hanford Company (1985).
  • R. E. EINZIGER and R. E. WOODLEY, “Predicting Spent Fuel Oxidation States in a Tuff Repository,” HEDL-SA-3627, Westinghouse Hanford Company (1987).
  • H. R. HOEKSTRA, A. SANTORO, and S. SIEGEL, “The Low Temperature Oxidation of UO2 and U4O9,” J. Inorg. Nucl. Chem., 18, 166 (1961).
  • T. WADSTEN, “The Oxidation of Polycrystalline Uranium Dioxide in Air at Room Temperature,” J. Nucl. Mater., 64, 315 (1977).
  • E. U. KUZ’MICHEVA, L. M. KOVBA, and E. A. IPPOLITOVA, “Oxidation of Uranium Dioxide at Temperatures Below 270°C,” Sov. Radiochem., 13, 877 (1971).
  • J. S. ANDERSON, L. E. J. ROBERTS, and E. A. HARPER, “The Oxides of Uranium. Part VII. The Oxidation of Uranium Dioxide,” J. Chem. Soc., 3946 (1955).
  • S. ARONSON, R. ROOF, and J. BELLE, “Kinetic Study of the Oxidation of Uranium Dioxide,” J. Chem. Phys., 27, 1 (1957).
  • P. E. BLACKBURN, J. WEISSBART, and E. A. GULBRANSEN, “Oxidation of Uranium Dioxide,” J. Phys. Chem., 62, 902 (1958).
  • D. E. Y. WALKER, “The Oxidation of Uranium Dioxides,” J. Appl. Chem., 15, 128 (1965).
  • P. TAYLOR, E. A. BURGESS, and D. G. OWEN, “An X-Ray Diffraction Study of the Formation of β-UO2.33 on UO2 Pellet Surfaces in Air at 229 to 275°C,” J. Nucl. Mater., 88, 153 (1980).
  • P. TEMPEST, P. TUCKER, and J. TYLER, “Oxidation of UO2 Fuel Pellets in Air at 503 and 543 K Studied Using X-Ray Photoelectron Spectroscopy and X-Ray Diffraction,” J. Nucl. Mater., 151, 251 (1988).
  • H. MATZKE, “Diffusion in Ceramic Oxide Systems,” Adv. Ceram., 17, 1 (1986).
  • H. MATZKE, “Atomic Transport Properties in UO2 and Mixed Oxides (U,Pu)O2,” J. Chem. Soc. Faraday Trans., 2, 83 (1987).
  • D. VOLLATH, “Transport Phenomena,” Gmelin Handbook, Vol. C5 (1986).
  • B. GRAMBOW, “Spent Fuel, Oxidation and Dissolution,” Technical Report 89-13, Swedish Nuclear Fuel and Waste Management Company (1989).
  • L. H. JOHNSON and D. W. SHOESMITH, “Spent Fuel,” Radioactive Waste Forms for the Future, W. LUTZE and R. EWING, Eds., Elsevier Science Publishing, New York (1988).
  • W. BREITUNG, “Oxygen Self and Chemical Diffusion Coefficients in UO2±x,” J. Nucl. Mater., 74, 10 (1978).
  • J. BRUNO, R. S. FORSYTH, and L. O. WERME, “Spent UO2 Fuel Dissolution, Tentative Modelling of Experimental Apparent Solubilities,” Mater. Res. Soc. Symp. Proc., 44, 413 (1985).
  • S. STROES-GASCOYNE et al., “Dissolution of Used CANDU Fuel at Various Temperatures and Redox Conditions,” Mater. Res. Soc. Symp. Proc., 50, 317 (1985).
  • J. BRUNO, “A Reinterpretation of the Solubility Product of UO2(S),” Acta Chem. Scand., 43, 99 (1989).
  • J. BRUNO and A. SANDINO, “The Solubility of Amorphous and Crystalline Schoepite in Neutral to Alkaline Solution,” Mater. Res. Soc. Symp. Proc., 127, 871 (1989).
  • K. OLLILA, “Dissolution Mechanism of UO2 at Various Parametric Conditions,” YJT-88-04, Nuclear Waste Commission of Finnish Power Companies (1988).
  • P. A. G. O’HARE, B. M. LEWIS, and S. N. NGUYEN, “Thermochemistry of Uranium Compounds XVII. Standard Molar Enthalpy of Formation at 298.15 K of Dehydrated Schoepite UO3.0 · 9H2O. Thermodynamics of (Schoepite + Dehydrated Schoepite + Water),” J. Chem. Thermodyn., 20, 1287 (1988).
  • D. W. SHOESMITH, S. SUNDER, B. M. IKEDA, and F. KING, “The Development of a Mechanistic Basis for Modelling Fuel Dissolution and Container Failures Under Waste Vault Conditions,” Mater. Res. Soc. Symp. Proc., 127, 279 (1989).
  • J. POSEY-DOWTY, E. AXTMANN, D. CRERAR, M. BORCSIK, A. RONK, and W. WOODS, “Dissolution Rate of Uraninite and Uranium Roll-Front Ores,” Econ. Geol., 82, 184 (1987).
  • D. W. SHOESMITH, S. SUNDER, M. G. BAILEY, G. J. WALLACE, and F. W. STANCHELL, “Anodic Oxidation of UO2. Part IV. X-Ray Photoelectron Spectroscopy and Electrochemical Studies of Film Growth in Carbonate-Containing Solutions,” Appl. Surface Sci., 20, 39 (1984).
  • S. SUNDER, D. W. SHOESMITH, L. H. JOHNSON, G. J. WALLACE, M. G. BAILEY, and A. P. SNAGLEWSKI, “Oxidation of CANDU Fuel by the Products of the Alpha Radiolysis of Groundwater,” Mater. Res. Soc. Symp. Proc., 84, 103 (1987).
  • C. N. WILSON, “Summary of Results from the Series 2 and Series 3 NNWSI Bare Fuel Dissolution Tests,” Mater. Res. Soc. Symp. Proc., 112, 473 (1988).
  • L. H. JOHNSON and H. H. JOLING, “The Dissolution of Irradiated Fuel Under Hydrothermal Conditions,” The Scientific Basis for Nuclear Waste Management, p. 321, S. V. TOPP, Ed., Elsevier Science Publishing Company (1982).
  • J. CRANK, The Mathematics of Diffusion, p. 117, Clarendon Press, Oxford (1955).
  • M. J. NICOL and C. R. S. NEEDES, “The Anodic Dissolution of Uranium Dioxide II. In Carbonate Solutions,” Electrochim. Acta., 22, 1381 (1977).
  • R. WANG, “Spent-Fuel Special Studies Progress Report: Probable Mechanism for Oxidation and Dissolution of Single-Crystal UO2 Surfaces,” PNL-3566, Battelle Pacific Northwest Laboratories (1981).
  • L. H. JOHNSON, D. W. SHOESMITH, G. E. LUNANSKY, M. G. BAILEY, and P. R. TREMAINE, “Mechanisms of Leaching and Dissolution of UO2 Fuel,” Nucl. Technol., 56, 238 (1982).
  • M. J. APTED, A. M. LIEBETRAU, and D. W. ENGEL, “The Analytical Repository Source-Term (AREST) Model: Analysis of Spent Fuel as a Nuclear Waste Form,” PNL-6347, Pacific Northwest Laboratories (1989).

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