Influence of Radiolysis on UO 2 Fuel Matrix Dissolution Under Disposal Conditions

The objective of this study was to examine the recent published literature on the influence of water radiolysis on UO2 fuel matrix dissolution under the disposal conditions. The -radiation is considered to be dominating over the other types of radiations at times longer than 1000 years. The presence of the anaerobic corrosion products of iron, especially of hydrogen, has been observed to play an important role under radiolysis conditions. It is not possible to exclude gamma/beta radiolysis effects in the experiments with spent fuel, since there is not available a fuel over 100 years old. More direct measurements of -radiolysis effects have been conducted with -doped UO2 materials. On the basis of the results of these experiments, a specific activity threshold to observe -radiolysis effects has been presented. The threshold is 1.8 · 10 to 3.3 · 10 Bq/g in anoxic 10 M carbonate solution. It is dependent on the environmental conditions, such as the reducing buffer capacity of the conditions. The results of dissolution rate measurements at VTT with U-doped UO2 samples in 0.01 to 0.1 M NaCl solutions under anoxic conditions did not show any effect of -radiolysis with doping levels of 5 and 10% U (3.2 · 10 and 6.3 · 10 Bq/g). Both Fe and hydrogen can act as reducing species and could react with oxidizing radiolytic species. Fe concentrations of the order of 10 M can decrease the rate of H2O2 production. Low dissolution rates, 2 · 10 to 2 · 10 /yr, have been measured in the presence of metallic Fe with 5 and 10% U-doped UO2 in 0.01 to 1 M NaCl solutions. The tests with isotope dilution method showed precipitation phenomena of U to occur during dissolution process. The concentrations of dissolved U were extremely low ( 8.4 · 10 M). No effects of -radiolysis could be seen. It is difficult to distinguish the effects of metallic Fe, Fe or hydrogen in these tests. Hydrogen could also act as a reducing agent. Interaction tests between U(VI) and Fe have shown the reduction of U(VI) hydroxide complexes to take place by Fe in aqueous solution. A decrease in corrosion and release rates has been observed in the experiments with spent fuel and alpha-doped UO2 in the presence of hydrogen. Hydrogen seems to suppress the oxidation and dissolution of UO2. The H2 concentration of around 10 M seemed to be a threshold for oxidation of UO2 to occur in the tests with 10% U-doped UO2 in 10 M NaCl (+2 · 10 M NaHCO3) solution. Dissolved hydrogen concentrations from the anaerobic corrosion of iron are estimated to be in the 10 to 10 M range. High burnup fuel did not seem to display any enhanced dissolution in the presence of 3.3 · 10 M H2. The level of U concentrations in solution has been very low in the presence of H2, ~ 10 M, lower than the solubility of amorphous UO2. The dissolved U concentrations at the same level have been measured in the presence of metallic Fe. A hypothesis of -radiation induced hydrogen annealing, or a crystallization process in the amorphous phase has been presented in literature to explain low U concentrations. A hypothetical mechanism to explain the effects of hydrogen under radiolysis conditions has been presented. The observations suggest that the consumption of oxidants is a surface-catalyzed process.

[1]  D. Shoesmith,et al.  The inhibiting effects of hydrogen on the corrosion of uranium dioxide under nuclear waste disposal conditions , 2005 .

[2]  V. Rondinella,et al.  Leaching Behaviour of Low -Activity Alpha-Doped UO2. , 2004 .

[3]  J. de Pablo,et al.  Combined effect of H2O2 and HCO3- on UO2(s) dissolution rates under anoxic conditions , 2009 .

[4]  G. Blondiaux,et al.  Oxidation and dissolution rates of UO2(s) in carbonate-rich solutions under external alpha irradiation and initially reducing conditions , 2006 .

[5]  M. Jonsson,et al.  On the catalytic effects of UO2(s) and Pd(s) on the reaction between H2O2 and H2 in aqueous solution , 2008 .

[6]  H. Christensen,et al.  Current State of Knowledge of Water Radiolysis Effects on Spent Nuclear Fuel Corrosion , 2000 .

[7]  J. Morse Aquatic chemical kinetics: Reaction rates of processes in natural waters , 1990 .

[8]  L. Werme,et al.  The anaerobic corrosion of carbon steel and cast iron in artificial groundwaters , 2001 .

[9]  H. Matzke,et al.  Leaching behaviour of UO2 containing α-emitting actinides , 2000 .

[10]  M. Jonsson,et al.  Oxidation of UO2 by radiolytic oxidants , 2003 .

[11]  K. Spahiu,et al.  Corrosion of high burn-up structured UO2 fuel in presence of dissolved H2 , 2009 .

[12]  D. Shoesmith,et al.  Oxidation and dissolution of nuclear fuel (UO2) by the products of the alpha radiolysis of water , 1997 .

[13]  D. Shuh,et al.  Resonant Inelastic Soft X-ray Scattering Studies of U(VI) Reduction on Iron Surfaces , 2003 .

[14]  D. Cui,et al.  The reduction of U(VI) on corroded iron under anoxic conditions , 2002 .

[15]  E. Myllykylä,et al.  Interaction Experiments Between U(VI) and Fe(II) in Aqueous Solution Under Anaerobic Conditions , 2008 .

[16]  M. Jonsson,et al.  Simulations of H2O2 concentration profiles in the water surrounding spent nuclear fuel taking mixed radiation fields and bulk reactions into account , 2008 .

[17]  Hans Wanner,et al.  Chemical thermodynamics of uranium , 1992 .

[18]  Y. Albinsson,et al.  Dissolution rates of unirradiated UO2, UO2 doped with 233U, and spent fuel under normal atmospheric conditions and under reducing conditions using an isotope dilution method , 2004 .

[19]  K. Spahiu,et al.  Corrosion of irradiated MOX fuel in presence of dissolved H2 , 2009 .

[20]  F. Clarens,et al.  Influence of β radiation on UO2 dissolution at different pH values , 2005 .

[21]  Kaija Ollila Dissolution of Unirradiated UO 2 and UO 2 Doped with 233 U in Low- and High-Ionic-Strength NaCl Under Anoxic and Reducing Conditions , 2008 .

[22]  C. Winterbourn,et al.  On the participation of higher oxidation states of iron and copper in Fenton reactions. , 1989, Free radical biology & medicine.

[23]  A. Poulesquen,et al.  Effect of alpha irradiation on UO2 surface reactivity in aqueous media , 2005 .

[24]  H. Christensen Calculation of Corrosion Rates of Alpha-Doped UO2 , 2006 .

[25]  M. Jonsson,et al.  Modelling of time resolved and long contact time dissolution studies of spent nuclear fuel in 10 mM carbonate solution – A comparison between two different models and experimental data , 2008 .

[26]  B. Hickel,et al.  The influence of water chemistry on the radiolysis of the primary coolant water in pressurized water reactors , 1999 .

[27]  J. de Pablo,et al.  UO2 dissolution in the presence of hydrogen peroxide at pH>11 , 2008 .

[28]  F. King,et al.  The effects of alpha-radiolysis on UO2 dissolution determined from electrochemical experiments with 238Pu-doped UO2 , 2002 .

[29]  J. C. Wren,et al.  Corrosion Behavior of Uranium Dioxide in Alpha Radiolytically Decomposed Water , 2005 .

[30]  S. Sunder,et al.  XPS studies of UO2 oxidation by alpha radiolysis of water at 100°C☆ , 1990 .

[31]  D. Cui,et al.  The fate of radiolytic oxidants during spent fuel leaching in the presence of dissolved near field hydrogen , 2004 .

[32]  L. Werme,et al.  The influence of near field hydrogen on actinide solubilities and spent fuel leaching , 2000 .

[33]  Aurora Martínez,et al.  Mechanisms governing the release of radionuclides from spent nuclear fuel in geological repository: major outcomes of the European Project SFS , 2006 .

[34]  David W. Shoesmith,et al.  Fuel corrosion processes under waste disposal conditions , 2000 .

[35]  M. Jonsson,et al.  Effects of HCO3- on the kinetics of UO2 oxidation by H2O2 , 2006 .

[36]  M. Amme Contrary effects of the water radiolysis product H2O2 upon th dissolution of nuclear fuel in natural ground water and deionized water , 2002 .

[37]  Leaching of Spent Fuel under Anaerobic and Reducing Conditions , 2002 .

[38]  Sara Nilsson,et al.  Radiation induced spent nuclear fuel dissolution under deep repository conditions. , 2007, Environmental science & technology.

[39]  H. Matzke,et al.  Corrosion and dissolution studies of UO2 containing α-emitters , 2002 .

[40]  J. Quiñones,et al.  An Experimental Study on the Influence of Gamma Radiation on Spent Fuel Dissolution in the Presence of a H 2 Atmosphere , 2004 .

[41]  D. Shoesmith,et al.  The influence of dissolved hydrogen on the surface composition of doped uranium dioxide under aqueous corrosion conditions , 2007 .

[42]  D. Cui,et al.  Surface mediated processes in the interaction of spent fuel α-doped UO2 with H2 , 2008 .

[43]  Virginia Oversby,et al.  Dissolution of Unirradiated UO 2 and UO 2 Doped with 233 U Under Reducing Conditions , 2005 .

[44]  M. Jonsson,et al.  The relative impact of radiolysis products in radiation induced oxidative dissolution of UO2 , 2006 .

[45]  E. Myllykylä,et al.  Interaction Between U(VI) and Fe(II) in Aqueous Solution Under Anaerobic Conditions - Closed System Experiments , 2011 .

[46]  D. Cui,et al.  On Mo-Ru-Tc-Pd-Rh-Te alloy particles extracted from spent fuel and their leaching behavior under Ar and H2 atmospheres , 2004 .

[47]  W. Bors,et al.  A kinetic study of UO2 dissolution and H2O2 stability in the presence of groundwater ions , 2007 .

[48]  Dissolution of irradiated fuel: a radiolytic mass balance study , 1995 .

[49]  D. Cui,et al.  Redox Reactions of Iron and Uranium Dioxide in Simulated Cement Pore Water Under Anoxic Conditions , 2002 .

[50]  The Effect of Hydrogen Peroxide Concentration on the Oxidative Dissolution of Unirradiated Uranium Dioxide , 2000 .

[51]  T. Eriksen,et al.  Experimental determination and chemical modelling of radiolytic processes at the spent fuel/water interface , 2000 .

[52]  K. Spahiu,et al.  Hydrogen suppresses UO2 corrosion , 2009 .

[53]  Stefan Röllin,et al.  Determination of dissolution rates of spent fuel in carbonate solutions under different redox conditions with a flow-through experiment , 2001 .

[54]  R. Guillaumont,et al.  Update on the chemical thermodynamics of uranium, neptunium, plutonium, americium and technetium , 2003 .

[55]  S. Stroes-Gascoyne,et al.  The Effect of Alpha-Radiolysis on UO 2 Dissolution Determined from Batch Experiments with 238 Pu-Doped UO 2 , 2004 .

[56]  D. Cui,et al.  The reduction of U(VI) by near field hydrogen in the presence of UO2(s) , 2004 .

[57]  S. Stroes-Gascoyne,et al.  The effects of alpha-radiolysis on UO2 dissolution determined from batch experiments with 238Pu-doped UO2 , 2005 .

[58]  D. Shoesmith Used Fuel and Uranium Dioxide Dissolution Studies - A Review , 2007 .

[59]  M. Jonsson,et al.  Modeling of the Effects of Radiolysis on UO 2 -dissolution Employing Recent Experimental Data , 2003 .

[60]  Volker Metz,et al.  Radionuclide release from high burnup spent fuel during corrosion in salt brine in the presence of hydrogen overpressure , 2005 .

[61]  M. Jonsson,et al.  Geometrical α- and β-dose distributions and production rates of radiolysis products in water in contact with spent nuclear fuel , 2006 .

[62]  Volker Metz,et al.  Effects of hydrogen and bromide on the corrosion of spent nuclear fuel and γ-irradiated UO2(s) in NaCl brine , 2008 .

[63]  A. Poulesquen,et al.  Effect of external gamma irradiation on dissolution of the spent UO2 fuel matrix , 2005 .

[64]  Mats Jonsson,et al.  Simulations of H2O2 concentration profiles in the water surrounding spent nuclear fuel , 2008 .

[65]  Laurent Charlet,et al.  Surface catalysis of uranium(VI) reduction by iron(II) , 1999 .