Dopant effect on the spent fuel matrix dissolution of new advanced fuels: Cr-doped UO2 and Cr/Al-doped UO2

被引:2
作者
Rodriguez-Villagra, N. [1 ]
Riba, O. [2 ]
Milena-Perez, A. [1 ]
Cobos, J. [1 ]
Jimenez-Bonales, L. [1 ]
Fernandez-Carretero, S. [1 ]
Coene, E. [2 ]
Silva, O. [2 ]
Duro, L. [2 ]
机构
[1] Ctr Invest Energet Medioambientales & Tecnol CIEMA, Avda Complutense 40, Madrid 28040, Spain
[2] Amphos 21 Consulting SL,C-Venezuela,103,2da Planta, Barcelona 08019, Spain
基金
欧盟地平线“2020”;
关键词
UO2; Leaching experiments; Deep geological repository; Chromium; Doping; Chromium-doped UO2; HYDROLYSIS CONSTANTS; OXIDATIVE DEHYDROGENATION; BURNABLE POISON; URANIUM-DIOXIDE; X-RAY; SOLUBILITY; SURFACE; CORROSION; KINETICS; HYDROGEN;
D O I
10.1016/j.jnucmat.2022.153880
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
To improve the fundamental understanding of the processes controlling spent fuel alteration under deep geological conditions, the influence of dopants (Cr and Cr/Al) on UO2 matrix stability is evaluated for "modern " types of light water reactor (LWR) fuels with additives. The uranium dissolution behavior of as-prepared 0.06 wt%Cr and 0.05 wt%Cr/0.02 wt%Al doped UO2 pellets is studied in simplified groundwater containing 19 mM HCO3- in autoclaves under hydrogen atmosphere. Sintered disks were exposed to simulated highly carbonated conditions, representative of a repository scenario of water intrusion after a hypothetical canister failure. The uranium concentration released was & SIM;10 -7 M for the 0.05 wt%Cr/0.02 wt%Al doped UO2 pellet and & SIM;10 -6 M for 0.06 wt%Cr doped UO2 pellets, after 170 days. The results indicate that the amount of dissolved uranium is slightly lower compared to previous studies in absence of a reductant gas phase, but clearly above the solubility of UO2(am, hyd). The initial measured pH was 8.9 +/- 0.1, which gradually approached a constant value of similar to 9.2 +/- 0.1. Solid characterization at the end of the dissolution experiment, by SEM, Raman spectroscopy and XRD shows that the surface of all pellets remains almost unaltered. The experimental results indicate a potential oxidative dissolution of UO2, which could be attributed to the presence/intrusion of dissolved oxygen in the prepared synthetic groundwater. In order to identify the mechanism of uranium release, the datasets from the batch experiments are simulated with a PHREEQC model previously calibrated with results of existing spent fuel UOx leaching experiments. The model includes the geochemical processes that are relevant for the studied experimental conditions: (i) non-oxidative dissolution of UO2, (ii) UO2 oxidation with O 2 , (iii) dissolution of U(VI) by carbonate water, (iv) reduction of oxidized U(VI) on the surface pellet by activated H2 . The ability to activate the dissolved H 2 is studied by implementing a kinetically controlled process of H 2 activation on the Cr surface in the model.(c) 2022 Published by Elsevier B.V.
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页数:10
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