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.
引用
收藏
页数:10
相关论文
共 64 条
[1]  
Alonso U., 2016, DFNRA15SP16
[2]  
[Anonymous], 2013, E11296 ASTM
[3]  
[Anonymous], 2010, IAEA ADV FUEL PELL M
[4]   Extent of oxidation of Cr(III) to Cr(VI) under various conditions pertaining to natural environment [J].
Apte, AD ;
Tare, V ;
Bose, P .
JOURNAL OF HAZARDOUS MATERIALS, 2006, 128 (2-3) :164-174
[5]   Advanced doped UO2 pellets in LWR applications [J].
Arborelius, Jakob ;
Backman, Karin ;
Hallstadius, Lars ;
Limbaeck, Magnus ;
Nilsson, Jimmy ;
Rebensdorff, Bjoern ;
Zhou, Gang ;
Kitano, Koji ;
Loefstroem, Reidar ;
Roennberg, Gunnar .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2006, 43 (09) :967-976
[6]  
BOHM W, 1987, KERNTECHNIK, V50, P234
[7]   Metrics for the Technical Performance Evaluation of Light Water Reactor Accident-Tolerant Fuel [J].
Bragg-Sitton, Shannon M. ;
Todosow, Michael ;
Montgomery, Robert ;
Stanek, Christopher R. ;
Montgomery, Rose ;
Carmack, W. Jon .
NUCLEAR TECHNOLOGY, 2016, 195 (02) :111-123
[8]   The influence of dissolved hydrogen on the surface composition of doped uranium dioxide under aqueous corrosion conditions [J].
Broczkowski, M. E. ;
Noel, J. J. ;
Shoesmith, D. W. .
JOURNAL OF ELECTROANALYTICAL CHEMISTRY, 2007, 602 (01) :8-16
[9]   The inhibiting effects of hydrogen on the corrosion of uranium dioxide under nuclear waste disposal conditions [J].
Broczkowski, ME ;
Noël, JJ ;
Shoesmith, DW .
JOURNAL OF NUCLEAR MATERIALS, 2005, 346 (01) :16-23
[10]   Adsorption of gases in multimolecular layers [J].
Brunauer, S ;
Emmett, PH ;
Teller, E .
JOURNAL OF THE AMERICAN CHEMICAL SOCIETY, 1938, 60 :309-319