Very high burnup spent fuel corrosion & leaching under hydrogen conditions
Source abstract
Abstract
This paper concerns a very high burnup UO2 spent nuclear fuel leaching experiment performed under high hydrogen pressure conditions (5 MPa H2 initially) in simplified granitic groundwater. Following an initial release after start-up the results demonstrate that the concentrations of redox sensitive elements such as Tc, U, Np and Pu stabilize at the solubility limits of their reduced oxide forms. The release of non-redox sensitive elements such as Cs also ceased within a year. Together these observations indicate that the hydrogen overpressure resulted in reducing conditions that suppresses fuel matrix corrosion. Following an initially rather rapid release of fission gases Kr and Xe, the release also ceases towards the end of the experiment, although at a surprisingly high released fraction of the inventory. In this experiment the fuel was cut from the rod, crushed in a vice and pre-leached under semi aerated conditions for 9 days before transitioning to conditions of high hydrogen overpressure and the resulting apparent inhibition of further corrosion or dissolution of the fuel matrix. These results are in contrast to our previous experiments with other portions of fuel from the same rod under similar hydrogen conditions, but with extensive dry milling and fuel corrosion in aerated conditions, prior to the transitions to hydrogen conditions. The results thus tentatively support the conclusion that preceding oxidation of the fuel surfaces may limit the potential for hydrogen to suppress fuel corrosion and dissolution.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: Radioactive element chemistry and processing · Nuclear Materials and Properties · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (60)
Show source-provided references
1. SKB, Fuel and canister process report for the safety assessment SR-Can. SKB Technical Report, TR-06-22, Svensk Kärnbränslehantering AB, 2006.
2. L. Agrenius, K. Spahiu, Criticality effects of long-term changes in material compositions and geometry in disposal canisters. SKB Technical Report, TR-16-06, Svensk Kärnbränslehantering AB, 2016.
3. Pressure building during early stages of gas production in a radioactive waste repository10.1016/S0022-3115(00)00184-7 ↗
4. Radiation effects on materials used in geological repositories for spent nuclear fuel10.5402/2012/639520 ↗
5. Corrosion of high burn-up structured UO2 fuel in presence of dissolved H210.1016/j.jnucmat.2009.07.004 ↗
6. Aqueous leaching of high burnup UO2 fuel under hydrogen conditions10.1557/adv.2018.273 ↗
7. The effect of temperature and fuel surface area on spent nuclear fuel dissolution kinetics under H2 atmosphere10.1016/j.jnucmat.2019.151981 ↗
8. Surface mediated process in the interaction of spent fuel or α-doped UO2 with H210.1557/PROC-1104-NN03-05 ↗
9. Fuel corrosion processes under waste disposal conditions10.1016/S0022-3115(00)00392-5 ↗
10. H2 inhibition of radiation induced oxidative dissolution of spent fuel10.1016/j.jnucmat.2008.09.021 ↗
11. Corrosion behavior of spent fuel in high pH solutions-effect of hydrogen10.1557/opl.2012.564 ↗
12. The corrosion of spent UO2 fuel in synthetic groundwater10.1016/0022-3115(86)90247-3 ↗
13. L.H. Johnson, The dissolution of irradiated UO2 fuel in groundwater. Report AECL-6837. Atomic Energy Canada Limited, Pinawa, Manitoba, Canada, 1982.
14. Anoxic corrosion of various high burnup samples10.1016/S0022-3115(96)00338-8 ↗
15. Spent fuel
16. R. Forsyth, The SKB Corrosion Programme. An evaluation of results from the experimental programme performed in the Studsvik Hot Cell Laboratory, SKB Technical Report, TR-97-25, Svensk Kärnbränslehantering AB, 1997.
17. Zwicky · 2011
18. Examining the conservatisms in dissolution rates of commercial spent nuclear fuel
19. Identification of the mechanism limiting the alteration of clad spent fuel segments in aerated carbonated groundwater10.1016/j.jnucmat.2004.01.008 ↗
20. Corrosion studies with high burn-up LWR fuel in simulated groundwater, MRS Symp
21. The effect of Y2O3 on the dynamics of oxidative dissolution of UO210.1016/j.jnucmat.2010.10.014 ↗
22. On the redox reactivity of doped UO2 pellets—influence of dopants on the H2O2 decomposition mechanism10.1016/j.jnucmat.2012.06.016 ↗
23. Radiation induced dissolution of (U, Gd)O2 pellets in aqueous solution - a comparison to standard UO2 pellets10.1016/j.jnucmat.2018.11.037 ↗
24. H. He, M. Broczkowski, K. O´Neil, D. Ofori, O. Semenikhin, D.W. Shoesmith, Corrosion of nuclear fuel (UO2) inside a failed nuclear waste container. NWMO TR-2012-09, Canada, 2012.10.1149/MA2012-02/21/2173 ↗
25. Influence of trivalent dopants on the structural and electrochemical properties of UO210.1149/2.047403jes ↗
26. The electrochemical study of Dy2O3 doped UO2 in slightly alkaline sodium carbonate/bicarbonate and phosphate solutions10.1016/j.electacta.2017.03.075 ↗
27. Influence of Gd doping on the structure and electrochemical behavior of UO210.1016/j.electacta.2017.07.006 ↗
28. The influence of near field hydrogen on actinide solubilities and spent fuel leaching10.1524/ract.2000.88.9-11.507 ↗
29. The influence of near field redox conditions on spent fuel leaching
30. The fate of radiolytic oxidants during spent fuel leaching in the presence of dissolved near field hydrogen10.1524/ract.92.9.625.54990 ↗
31. A. Loida, B. Grambow, H. Geckeis, Spent fuel corrosion behavior in salt solution in the presence of hydrogen overpressure, Proc. of ICEM'01: The 8th Internat. Conf. on Radioactive Waste Management and Environmental Remediation, Bruges, Belgium, 2011.
32. P. Carbol, J. Cobos-Sabate, J-P. Glatz, B. Grambow, B. Kienzler, A. Loida, A. Martinez Esparza, V. Metz, J. Quiñones, C. Ronchi, V. Rondinella, K. Spahiu (eds), D.H. Wegen, T. Wiss, The effect of dissolved hydrogen on the dissolution of 233U doped UO2(s), high burn-up spent fuel and MOX fuel. SKB TR-05-09, Svensk Kärnbränslehantering AB, 2005.
33. Radionuclide release from high burnup spent fuel during corrosion in salt brine in the presence of hydrogen overpressure10.1016/j.jnucmat.2005.05.020 ↗
34. Corrosion of irradiated MOX fuel in presence of dissolved H210.1016/j.jnucmat.2009.03.044 ↗
35. The high burn-up structure in nuclear fuel10.1016/S1369-7021(10)70221-2 ↗
36. The chemistry/electrochemistry of spent nuclear fuel as a waste form
37. Guillamont · 2003
38. Contribution of energetically reactive surface features to the dissolution of CeO2 and ThO2 analogues for spent nuclear fuel microstructures10.1021/am5018978 ↗
39. Lessons learned from leaching of dry milled high burnup UO2 fuel under H2 atmosphere10.1557/adv.2017.205 ↗
40. Tait · 1997
41. The influence of calcium ions on the development of acidity in corrosion products deposits on SIMFUEL, UO210.1016/j.jnucmat.2006.02.002 ↗
42. The influence of silica on the development of acidity in corrosion products deposits on SIMFUEL(UO2)10.1016/j.corsci.2006.02.012 ↗
43. 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 ↗
44. Determination of fission gas release of spent nuclear fuel in puncturing test and leaching experiments under anoxic conditions10.1016/j.jnucmat.2016.06.035 ↗
45. H. Assman, Advantages of oxidative UO2 sintering process “NIKUSI”, European Nuclear Society Meeting (ENS´86), Geneva, Switzerland, June 1-6, 1986.
46. LWR spent fuel storage behaviour10.1016/0022-3115(86)90219-9 ↗
47. Rapid aqueous release of fission products from high burn-up LWR fuel: experimental results and correlations with fission gas release10.1016/j.jnucmat.2011.09.007 ↗
48. The inhibiting effects of hydrogen on the corrosion of uranium dioxide under nuclear waste disposal conditions10.1016/j.jnucmat.2005.04.070 ↗
49. Radiation induced spent nuclear fuel dissolution under deep repository conditions10.1021/es070832y ↗
50. On the effects of fission product noble metal inclusions on the kinetics of radiation induced dissolution of spent nuclear fuel10.1016/j.jnucmat.2008.04.018 ↗
51. Oxidation of UO2(s) in aqueous solutions
52. Modelling of time resolved and long contact time dissolution studies of spent nuclear fuel in 10 mM carbonate-A comparison between two models and experimental data10.1016/j.jnucmat.2007.12.003 ↗
53. A model for the influence of steel corrosion products on nuclear fuel corrosion under permanent disposal conditions10.1016/j.corsci.2012.04.027 ↗
54. Modelling the radiolytic corrosion of α-doped UO2 and spent nuclear fuel10.1016/j.jnucmat.2017.07.011 ↗
55. Roles of radiolytic and externally generated H2 in the corrosion of fractured spent fuel10.1021/acs.est.6b04167 ↗
56. Resolving the H2 effect on radiation induced dissolution of UO2-based spent nuclear fuel10.1016/j.jnucmat.2009.10.067 ↗
57. Sorption coefficients and molecular mechanisms of Pu, U, Np, Am and Tc to Fe (hydr)oxides10.1016/j.jhazmat.2012.09.011 ↗
58. Compilation of radionuclide sorption coefficients for performance assessment
59. Spent fuel corrosion and the impact of iron corrosion – the effects of hydrogen generation and formation of iron corrosion products
60. Leaching of spent nuclear fuels in aerated conditions: influences of sample preparation on radionuclide release patterns10.1016/j.jnucmat.2019.151789 ↗