New radiolysis-driven matrix dissolution operational model based on stationary UO2 voltametric experiments

1. Spent fuel

2. Fuel corrosion processes under waste disposal conditions10.1016/S0022-3115(00)00392-5 ↗

3. Instant release fraction and matrix release of high burn-up UO2 spent nuclear fuel: effect of high burn-up structure and leaching solution composition10.1016/j.jnucmat.2012.04.036 ↗

4. Instant release of fission products in leaching experiments with high burn-up nuclear fuels in the framework of the Euratom project FIRST-Nuclides10.1016/j.jnucmat.2016.10.048 ↗

5. Quantitative assessment of the instant release fraction (IRF) for fission gases and volatile elements as a function of burnup and time under geological disposal conditions10.1557/PROC-807-35 ↗

6. Spent fuel radionuclide source-term model for assessing spent fuel performance in geological disposal. Part I: Assessment of the instant release fraction10.1016/j.jnucmat.2005.04.071 ↗

7. Solubility and solubility product at 22°C of UO2(c) precipitated from aqueous U(IV) solutions10.1023/A:1022671530250 ↗

8. Some uses for natural analogues in assessing the function of a HLW repository10.1016/0009-2541(86)90022-7 ↗

9. Oxidation of UO2 fuel by the products of γ radiolysis of water10.1016/0022-3115(92)90078-Y ↗

10. Effect of alpha radiolysis on doped UO2 dissolution under reducing conditions10.1524/ract.92.9.611.55010 ↗

11. UO2 under reducing conditions and the influence of an oxidized surface layer (UO2+x): application of a continuous flow-through reactor10.1016/0016-7037(91)90330-8 ↗

12. Solubility and oxidation state of uranium under anoxic conditions (N2 atmosphere)10.1524/ract.1996.74.special-issue.9 ↗

13. Uranium secondary phase formation during anoxic hydrothermal leaching processes of UO2 nuclear fuel10.1016/j.jnucmat.2005.02.004 ↗

14. A.O. Allen, “The Radiation Chemistry of Water and Aqueous Solutions”, Van Nostrand: New York, 1961.

15. Spinks · 1990

16. Current state of knowledge of water radiolysis effects on spent nuclear fuel corrosion10.13182/NT00-A3107 ↗

17. Ten-year results from unsaturated drip tests with UO2 at 90°C: implications for the corrosion of spent nuclear fuel10.1016/S0022-3115(96)00383-2 ↗

18. Chemical thermodynamics of uranium volume 1

19. Spent fuel radionuclide source term model for assessing spent fuel performance in geological disposal. Part II: Matrix alteration model and global performance10.1016/j.jnucmat.2005.05.021 ↗

20. Electrochemical aspects of radiolytically enhanced UO2 dissolution10.1524/ract.92.9.603.54977 ↗

21. Calculations simulating spent-fuel leaching experiments10.13182/NT98-A2916 ↗

22. D.W. Shoesmith Used Fuel and Uranium Dioxide Dissolution Studies–A Review NWMO TR-2007–03 July 2007.10.5006/C2008-08RTS04 ↗

23. Modelling the radiolytic corrosion of α-doped UO2 and spent nuclear fuel10.1016/j.jnucmat.2017.07.011 ↗

24. A model for the influence of steel corrosion products on nuclear fuel corrosion under permanent disposal conditions10.1016/j.corsci.2012.04.027 ↗

25. An improved model for the corrosion of used nuclear fuel inside a failed waste container under permanent disposal conditions10.1016/j.corsci.2014.03.019 ↗

26. The relative impact of radiolysis products in radiation induced oxidative dissolution of UO210.1016/j.jnucmat.2006.04.001 ↗

27. Addition versus radiolytic production effects of hydrogen peroxide on aqueous corrosion of UO210.1016/j.jnucmat.2005.05.009 ↗

28. Effect of alpha irradiation on UO2 surface reactivity in aqueous media radiochim

29. Oxidation and dissolution rates of UO2(s) in carbonate-rich solutions under external α irradiation and initially reducing conditions10.1524/ract.2006.94.9-11.567 ↗

30. C. Poinssot, C. Ferry, M. Kelm, B. Grambow, A. Martinez-Esparza, L. Johnson, Z. Adriambololona, J..Bruno, C. Cachoir, J.M. Cavedon, H. Christensen, C. Corbel, C. Jégou, K. Lemmens, A. Loida, P. Lovera, F. Miserque, J. de Pablo, A. Poulesquen, J. Quinones, V. Rondinella, K. Spahiu, D. Wegen, “Spent fuel stability under repository conditions – Final Report of the European project”, CEA-R-6093 CEA, Saclay, France (2004).

31. A mixed-potential model to predict fuel (uranium dioxide) corrosion within a failed nuclear waste container10.5006/1.3277609 ↗

32. Electrochemical studies of SIMFUELS10.1016/0925-8388(94)90985-7 ↗

33. C. Gaulard, " Influence de l′environnement sur l′altération de la matrice UO2 du combustible irradié ", Thèse de doctorat de l′Université d′Evry Val d′Essonne, (2012).

34. Kinetics of oxidation and dissolution of uranium dioxide in aqueous acid solutions10.1016/j.electacta.2012.04.022 ↗

35. The anodic dissolution of uranium dioxide – I. In perchlorate solutions10.1016/0013-4686(75)80009-0 ↗

36. The anodic dissolution of uranium dioxide – II. In carbonate solutions10.1016/0013-4686(77)85147-5 ↗

37. The electrochemical reduction of hydrogen peroxide on uranium dioxide under intermediate pH to acidic conditions10.1016/j.electacta.2008.03.008 ↗

38. 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 ↗

39. O.L. Rasmussen, E. Bjergbakke,“CHEMSIMUL A Program Package for Numerical Simulation of Chemical Reaction Systems, 1984 Risø R395.

40. P. Kirkegaard, E. Bjergbakke, J.V. Olsen, “A chemical kinetics software package”, Risø DTU, (2008), ISBN 978–87-550–3653-6 Risø-R-1630.

41. A comprehensive model to describe radiolytic processes in cement medium10.1016/j.jnucmat.2006.10.004 ↗

42. P. Kirkegaard, E. Bjergbakke, J.V. Olsen, CHEMSIMUL: A chemical kinetics software package, 2007, 〈http://www.chemsimul.dk〉, Risø National Laboratory.

43. An evaluation of water layer thickness effective in the oxidation of UO2 fuel due to radiolysis of water10.1016/S0022-3115(96)00342-X ↗

44. Oxidation of nuclear fuel (UO2) by the products of water radiolysis: development of a kinetic model10.1016/0925-8388(94)90886-9 ↗

45. B. Grambow, J. Bruno, L. Duro, J. Merino, A. Tamaya, C. Martin, G. Pepin, S. Schumacher, O. Smidt, C. Ferry, C. Jégou, J. Quinones, E. Iglesias, N. Rodriguez Villagra, J.M. Nieto, A. Martinez-Esparza, A. Loida, V. Metz, B. Kienzler, G. Bracke, D. Pellegrini, G. Mathieu, V. Wasselin-Trupin, C. Serres, D. Wegen, M. Jonsson, L. Johnson, K. Lemmens, J. Liu, K. Spahiu, E. Ekeroth, I. Casas, J. de Pablo, C. Watson, P. Robinson, D. Hodgkinson, Model uncertainty for the mechanism of dissolution of spent fuel in nuclear waste repository, (2010), Project MICADO Final Activity Report NUWASTE-2005/6–3.2.1.1-2.

46. Electrochemical studies of the effect of H2 on UO2 dissolution

47. User’s guide to PHREEQC (Version 2)-a computer program for speciation, batch-reaction, one-dimensional transport, and inverse geochemical calculations: U.S. Geological Survey Water-Resources Investigations

48. S.R. Charlton, D.L. Parkhurst, Modules Based on the Geochemical Model PHREEQC for Use in Scripting and Programming Languages”, Computers & Geosciences, 2011, Version 3.4.0.

49. CRC Handbook of Chemistry and Physics—69th Edition, 1988–1989, https://doi.org/10.1002/jctb.280500215.10.1002/jctb.280500215 ↗

50. Andra thermodynamic database for performance assessment: ThermoChimie10.1016/j.apgeochem.2014.05.007 ↗

51. In situ characterization of the Callovo-Oxfordian pore water composition10.1016/j.pce.2008.10.048 ↗

52. A thermodynamic model for the prediction of pore water composition of clayey rock at 25 and 80°C - comparison with results from hydrothermal alteration experiments10.1016/j.chemgeo.2012.09.040 ↗

53. Comment on “On the influence of carbonate in mineral dissolution: 1. The thermodynamics and kinetics of hematite dissolution in bicarbonate solutions at T = 25°C by J. Bruno, W. Stumm, P. Wersin, and F. Brandberg”10.1016/S0016-7037(00)00327-6 ↗

54. P. Blanc, Thermoddem: Sélection de propriétés thermodynamiques pour les principales espèces aqueuses et minérales porteuses de fer. Rapport final, BRGM/RP-56787-FR 2008.

55. Reagents for high temperature aqueous chemistry: trifluoromethanesulfonic acid and its salts10.1139/v75-433 ↗

56. The molal dissociation quotients of water in sodium trifluoromethanesulfonate solutions to high temperatures10.1007/BF00646434 ↗

57. J. Verastegui, G. Durand et B. Tremillon, " Electrochimie dans l′acide trifluorométhanesulfonique: caractéristiques électrochimiques du solvant ", Electroanalytical Chemistry and lnterfacial Electrochemistry, 54 (1974), 269–277.10.1016/0368-1874(74)87078-4 ↗

58. On the reduction of ClO4- ions in the course of metal dissolution in HClO4 solutions10.1016/S0010-938X(02)00104-X ↗

59. Spectrophotometric determination of uranium with 4-(2pyridylazo)resorcinol10.1021/ac60204a020 ↗

60. Spectrophotometric determination of uranium(IV) with potassium iron (III) cyanide10.1021/ac60320a034 ↗

61. A.J. Bard, L.R. Faulkner, R. Rosset, D. Bauer, Electrochimie: Principes, méthodes et applications, Edition Masson, 1983.

62. K. Lemmens, C. Cachoir, T. Mennecart, Dissolution behavior of spent nuclear fuel at highly alkaline conditions. Phenomenological synthesis report”, SCK•CEN/27622175, 2019.

63. K. Ollila, Dissolution of unirradiated UO2 and UO2 dopped with 233U in 0.01 M NaCl under anoxic and reducing conditions, POSIVA 2006–08, , 2006.

64. K. Ollila, Dissolution of unirradiated UO2 and UO2 doped with 233U in low- and high-ionic-strength NaCl under anoxic and reducing conditions, Deliverable NF-PRO and POSIVA 2008–50, 2008.

65. Radiolytic oxidation of UO2 pellets doped with alpha-emitters (Pu-238/239)10.1016/j.jallcom.2007.12.054 ↗