Modelling uranium dioxide corrosion under repository conditions: A pore-scale study of the chemical and thermal processes
Source abstract
Abstract
Abstract This paper investigates the corrosion behaviors of spent uranium dioxide (UO2) fuel when placed in geological repositories. We performed pore-scale reactive transport simulations of the UO2 corrosion process in a defective fuel rod with different orientations of breach or fracture on its clad. It is found that the corrosion rate has strong dependency on the breach orientation. The highest corrosion rate of UO2 is calculated when the angle between the groundwater flow direction and the clad fracture reaches 180°. UO2 corrosion simulations with different flow rates are compared. The results show the higher flow rate accelerates the corrosion of UO2 fuel. The effect of pH on the corrosion process is also determined. It is indicated that higher pH can limit the corrosion of UO2 by reducing the reaction rate. The dependence of reaction rate and time on reactive surface area is explored. Spent fuel with lower surface area demonstrates longer lifetime under corrosion conditions. A numerical model coupling thermal conduction and chemical reactions is developed to assess the impact of temperature on the process of UO2 corrosion. The results show that higher temperature leads to larger corrosion rates for UO2. The predicted reaction rates are higher in comparison with the isothermal results. Hence, our results can help improve the fundamental understanding of UO2 corrosion in geological repositories for long-term storage of spent nuclear fuels and provide guidance for the safe operations and selection of appropriate repositories.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (74)
Show source-provided references
1. Nuclear waste canister materials: corrosion behavior and long-term performance in geological repository systems
2. Parametric study of LWR spent fuel dissolution kinetics10.1016/0022-3115(92)90074-U ↗
3. Corrosion of uranium dioxide in hydrogen peroxide solutions10.1016/j.corsci.2003.09.005 ↗
4. Energetics of hydration on uranium oxide and peroxide surfaces
5. Fractionation of REE, U, and Th in natural ore-forming hydrothermal systems: Thermodynamic modeling10.1016/j.jct.2018.08.032 ↗
6. Kinetic study of the oxidative dissolution of UO2 in aqueous carbonate media10.1021/ie049457y ↗
7. Sunder · 1991
8. Kinetics of corrosion and dissolution of uranium dioxide as a function of pH10.1002/(SICI)1097-4601(1997)29:4<261::AID-KIN4>3.0.CO;2-S ↗
9. Multidimensional multiphysics simulation of nuclear fuel behavior10.1016/j.jnucmat.2012.01.012 ↗
10. Modelling of the UO 2 dissolution mechanisms in synthetic groundwater solutions
11. Calculation of used nuclear fuel dissolution rates under anticipated Canadian waste vault conditions10.1016/S0022-3115(97)00272-9 ↗
12. The oxidative dissolution of unirradiated UO2 by hydrogen peroxide as a function of pH10.1016/j.jnucmat.2005.06.002 ↗
13. Intercomparison of reactive transport models applied to UO2 oxidative dissolution and uranium migration10.1016/S0169-7722(02)00127-4 ↗
14. The corrosion of nuclear fuel (UO2) in oxygenated solutions10.1016/0010-938X(89)90048-6 ↗
15. The oxidative dissolution mechanism of uranium dioxide. The effect of pH and oxygen partial pressure
16. Effect of H2O2, NaClO and Fe on the dissolution of unirradiated UO2 in NaCl 5 mol kg− 1. Comparison with spent fuel dissolution experiments10.1016/S0022-3115(96)00341-8 ↗
17. Fuel corrosion processes under waste disposal conditions10.1016/S0022-3115(00)00392-5 ↗
18. The relative impact of radiolysis products in radiation induced oxidative dissolution of UO210.1016/j.jnucmat.2006.04.001 ↗
19. Radiolytic oxidation of UO2 pellets doped with alpha-Emitters (238/239Pu)10.1016/j.jallcom.2007.12.054 ↗
20. Corrosion and dissolution studies of UO2 containing α-emitters10.1524/ract.2002.90.9-11_2002.597 ↗
21. Effect of external gamma irradiation on dissolution of the spent UO2 fuel matrix10.1016/j.jnucmat.2005.01.008 ↗
22. Modelling the radiolytic corrosion Of A-Doped UO2 And Spent Nuclear Fuel10.1016/j.jnucmat.2017.07.011 ↗
23. Effect of metallic iron on the oxidative dissolution of UO2 doped with a radioactive alpha emitter in synthetic Callovian-Oxfordian groundwater10.1016/j.gca.2017.08.043 ↗
24. Reactive transport modeling: a key performance assessment tool for the geologic disposal of nuclear waste10.2138/gselements.15.2.99 ↗
25. Fluid flow and reactive transport around potential nuclear waste emplacement tunnels at Yucca Mountain, Nevada10.1016/S0169-7722(02)00183-3 ↗
26. Roles of radiolytic and externally generated H2 in the corrosion of fractured spent nuclear fuel10.1021/acs.est.6b04167 ↗
27. Geological disposal of nuclear waste: a primer10.2113/gselements.12.4.233 ↗
28. Long-term storage of spent nuclear fuel10.1038/nmat4226 ↗
29. The oxidative dissolution mechanism of uranium dioxide. I. The effect of temperature in hydrogen carbonate medium10.1016/S0016-7037(99)00237-9 ↗
30. Jernkvist · 2004
31. A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents10.1016/j.net.2015.03.004 ↗
32. Pore‐scale simulation of carbonate dissolution in micro‐CT images10.1002/2015JB012117 ↗
33. Numerical simulation of reactive transport on micro-CT images10.1007/s11004-016-9640-3 ↗
34. Lattice Boltzmann pore‐scale model for multicomponent reactive transport in porous media
35. Finite-difference approximation for fluid-flow simulation and calculation of permeability in porous media10.1007/s11242-012-0024-y ↗
36. Pore scale modeling of immiscible and miscible fluid flows using smoothed particle hydrodynamics10.1016/j.advwatres.2005.11.014 ↗
37. Impact of mineralogical heterogeneity on reactive transport modelling10.1016/j.cageo.2017.03.020 ↗
38. Characterisation of reactive transport in pore-scale correlated porous media10.1016/j.ces.2017.06.044 ↗
39. Pore-scale simulation of dissolution-induced variations in rock mechanical properties10.1016/j.ijheatmasstransfer.2017.04.049 ↗
40. Pore-scale study of diffusion–reaction processes involving dissolution and precipitation using the lattice Boltzmann method10.1016/j.ijheatmasstransfer.2014.03.074 ↗
41. Pore-scale modeling of multiphase reactive transport with phase transitions and dissolution-precipitation processes in closed systems10.1103/PhysRevE.87.043306 ↗
42. Pore-scale modelling of CO 2 storage in fractured coal10.1016/j.ijggc.2017.09.007 ↗
43. Pore-scale simulation of multicomponent multiphase reactive transport with dissolution and precipitation10.1016/j.ijheatmasstransfer.2015.02.035 ↗
44. High-resolution pore-scale simulation of dissolution in porous media10.1016/j.ces.2016.12.064 ↗
45. Numerical simulation of fluid-fluid-solid reactions in porous media10.1016/j.ijheatmasstransfer.2017.11.141 ↗
46. Sahimi · 2011
47. Determination of dissolution rates of spent fuel in carbonate solutions under different redox conditions with a flow-through experiment10.1016/S0022-3115(01)00645-6 ↗
48. Electrochemistry of UO2 nuclear fuel
49. Pellet-clad interaction (PCI) failures of zirconium alloy fuel cladding—a review10.1016/0022-3115(90)90282-R ↗
50. Ollila · 1999
51. Molecular dynamics calculations of aqueous uranyl carbonate species diffusion10.1016/j.gca.2010.06.007 ↗
52. Correlation of diffusion coefficients in dilute solutions10.1002/aic.690010222 ↗
53. Dagan · 2005
54. Rounds · 2013
55. Uranium (VI) speciation diagrams in the UO 2 2+/CO 3 2-/H 2 O system at 25° C
56. Gómez · 2008
57. Specific surface area of swaged UO2 compact10.1080/18811248.1965.9732146 ↗
58. Frost · 2013
59. Wilson · 1996
60. Pore‐space structure and average dissolution rates: a simulation study10.1002/2016WR019313 ↗
61. Mass transfer and problems of secondary porosity creation in deeply buried hydrocarbon reservoirs10.1016/0264-8172(87)90044-4 ↗
62. The effect of pH on the corrosion of nuclear fuel (UO2) in oxygenated solutions10.1016/0010-938X(91)90120-E ↗
63. Experimental determination of UO2 (cr) dissolution kinetics: Effects of solution saturation state and pH10.1016/j.jnucmat.2005.05.012 ↗
64. Limited · 1988
65. Variation of solubility, biokinetics and dose coefficient of industrial uranium oxides according to the specific surface area10.1093/oxfordjournals.rpd.a033039 ↗
66. Ikonen · 2003
67. Bobkov · 2008
68. Hedin · 1997
69. Pore scale modeling of reactive transport involved in geologic CO 2 sequestration10.1007/s11242-009-9443-9 ↗
70. Delegard · 2008
71. Mrowec · 1980 · Vol. 5
72. Synthesis, structure determination, and aqueous durability of Cs2ZrSi3O910.1111/j.1151-2916.2001.tb00623.x ↗
73. Energetics of Substituted Pollucites Along the CsAlSi2O6–CsTiSi2O6. 5 Join: A High‐Temperature Calorimetric Study10.1111/j.1151-2916.2001.tb00697.x ↗
74. Thermochemistry of microporous silicotitanate phases in the Na {sub 2} O-Cs {sub 2} O-SiO {sub 2}-TiO {sub 2}-H {sub 2} O system