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Articles de revues sur le sujet « UO2 Cr doped »

Auteur : Grafiati
Publié le 1 mars 2025

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1

Cachoir, Christelle, Thierry Mennecart, and Karel Lemmens. "Evolution of the uranium concentration in dissolution experiments with Cr-(Pu) doped UO2 in reducing conditions at SCK CEN." MRS Advances 6, no. 4-5 (2021): 84–89. http://dx.doi.org/10.1557/s43580-021-00027-y.

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AbstractCr-doped UO2-based model materials were prepared at SCK CEN, mimicking modern LWR fuels, to understand the influence of Cr doping on the spent fuel dissolution behaviour in geological repository conditions. Tests were carried out with four model materials: depleted UO2, Cr-doped depleted UO2, Pu-doped UO2 and Pu-Cr-doped UO2. Static dissolution experiments have been performed up to 4 months in autoclaves under 10 bar H2 pressure with a Pt/Pd catalyst in media at pH 13.5 and at pH 9. The Cr-doping appeared to reduce the U concentrations by a factor 6 at pH 13.5, but it had no or not muc
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Cordara, Theo, Hannah Smith, Ritesh Mohun, et al. "Hot Isostatic Pressing (HIP): A novel method to prepare Cr-doped UO2 nuclear fuel." MRS Advances 5, no. 1-2 (2020): 45–53. http://dx.doi.org/10.1557/adv.2020.62.

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ABSTRACTThe addition of Cr2O3 to modern UO2 fuel modifies the microstructure so that, through the generation of larger grains during fission, a higher proportion of fission gases can be accommodated. This reduces the pellet-cladding mechanical interaction of the fuel rods, allowing the fuels to be “burned” for longer than traditional UO2 fuel, thus maximising the energy obtained. We here describe the preparation of UO2 and Cr-doped UO2 using Hot Isostatic Pressing (HIP), as a potential method for fuel fabrication, and for development of analogue materials for spent nuclear fuel research. Chara
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Kegler, Philip, Martina Klinkenberg, Andrey Bukaemskiy, et al. "Chromium Doped UO2-Based Ceramics: Synthesis and Characterization of Model Materials for Modern Nuclear Fuels." Materials 14, no. 20 (2021): 6160. http://dx.doi.org/10.3390/ma14206160.

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Cr-doped UO2 as a modern nuclear fuel type has been demonstrated to increase the in-reactor fuel performance compared to conventional nuclear fuels. Little is known about the long-term stability of spent Cr-doped UO2 nuclear fuels in a deep geological disposal facility. The investigation of suitable model materials in a step wise bottom-up approach can provide insights into the corrosion behavior of spent Cr-doped nuclear fuels. Here, we present new wet chemical approaches providing the basis for such model systems, namely co-precipitation and wet coating. Both were successfully tested and opt
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Kegler, Philip, Martina Klinkenberg, Felix Brandt, Guido Deissmann, and Dirk Bosbach. "Evaluation of the corrosion behavior of modern spent nuclear fuels under repository conditions." Safety of Nuclear Waste Disposal 1 (November 10, 2021): 91–93. http://dx.doi.org/10.5194/sand-1-91-2021.

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Abstract. In Germany it is planned to directly dispose spent nuclear fuel (SNF) from nuclear power plants together with other high-level radioactive wastes (HLW) from former SNF reprocessing (e.g., vitrified waste), in a deep geological repository for heat-generating wastes – the siting process for this repository was started in 2017 and is ongoing. Based on several decades of research, development, and demonstration (RD&D) it is generally accepted at the technical and scientific level that direct disposal of HLW and SNF in deep mined geological repositories is the safest and most sust
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Zacharie-Aubrun, Isabelle, Rebecca Dowek, Jean Noirot, Thierry Blay, Martiane Cabié, and Myriam Dumont. "Restructuring in high burn-up UO2 fuels: Experimental characterization by electron backscattered diffraction." Journal of Applied Physics 132, no. 19 (2022): 195903. http://dx.doi.org/10.1063/5.0104865.

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This paper discusses the use of electron backscattered diffraction to characterize restructuring in a set of UO2 samples, irradiated in a pressurized water reactor at a burn-up between 35 and 73 GWd/tU, including standard UO2 samples and Cr-doped UO2 samples, to provide a better understanding of restructuring occurring both on the periphery and in the center of high-burn-up pellets. The formation of a high burn-up structure on the periphery of high burn-up UO2 was confirmed in our experiment. We found restructuring associated with bubble formation of all the samples in the central area, with h
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Cooper, M. W. D., D. J. Gregg, Y. Zhang, et al. "Formation of (Cr,Al)UO4 from doped UO2 and its influence on partition of soluble fission products." Journal of Nuclear Materials 443, no. 1-3 (2013): 236–41. http://dx.doi.org/10.1016/j.jnucmat.2013.07.038.

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Gonzalez, Jheffry, and Martin Ševecek. "Modelling of fission gas release in UO2 doped fuel using transuranus code." Acta Polytechnica CTU Proceedings 37 (December 6, 2022): 24–30. http://dx.doi.org/10.14311/app.2022.37.0024.

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The expected benefits from Cr-doped fuel are improved retention of fission gases within the pellets due to its large grain size. To demonstrate this, several experiments have been carried out by Halden reactor and Studsvik. These experiments are now being used to benchmark several fuel performance codes among them transuranus code. All this as part of a Coordinate Research Project (CRP) by IAEA named Testing and Simulation for Advanced Technology and Accident Tolerant Fuels (ATF-TS). This work is introducing a novel fission gas diffusivity model for doped fuel in transuranus code. It is observ
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Terricabras, Adrien J., Sean M. Drewry, Keri Campbell, et al. "Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO2." Journal of Nuclear Materials 594 (June 2024): 155022. http://dx.doi.org/10.1016/j.jnucmat.2024.155022.

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Curti, Enzo, and Dmitrii A. Kulik. "Oxygen potential calculations for conventional and Cr-doped UO2 fuels based on solid solution thermodynamics." Journal of Nuclear Materials 534 (June 2020): 152140. http://dx.doi.org/10.1016/j.jnucmat.2020.152140.

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Introïni, Clément, Jérôme Sercombe, Christine Guéneau, and Bo Sundman. "Modeling oxygen transport in Cr doped UO2 fuel with the TAF-ID during power transients." Journal of Nuclear Materials 603 (January 2025): 155352. http://dx.doi.org/10.1016/j.jnucmat.2024.155352.

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de Lara, A., P. Van Uffelen, G. Nicodemo, G. Zullo, D. Pizzocri, and E. Shwageraus. "Consideration of Cr-doped UO2 fuel performance for a Fluoride-Cooled High Temperature Reactor concept." Annals of Nuclear Energy 209 (December 2024): 110820. http://dx.doi.org/10.1016/j.anucene.2024.110820.

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Gorton, Jacob P., Annabelle G. Le Coq, Zane G. Wallen, et al. "Modeling and design of a separate effects irradiation test targeting fission gas release from Cr-doped UO2." Nuclear Engineering and Design 429 (December 2024): 113571. http://dx.doi.org/10.1016/j.nucengdes.2024.113571.

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Noirot, Jean, Rébecca Dowek, Isabelle Zacharie-Aubrun, Thierry Blay, Martiane Cabié, and Myriam Dumont. "Restructuring in high burn-up pressurized water reactor UO2 fuel central parts: Experimental 3D characterization by focused ion beam—scanning electron microscopy." Journal of Applied Physics 132, no. 19 (2022): 195902. http://dx.doi.org/10.1063/5.0105072.

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Focussed ion beam - scanning electron microscope (FIB-SEM) 3D examination was conducted on three standard UO2 and one Cr doped UO2 high burn-up pressurized water reactor (PWR) fuel samples. This work complemented other microanalysis examination, including an electron backscattered diffraction (EBSD) work on the polished surface. A parallel article giving the EBSD results was submitted simultaneously. Together, they found, in all the central area of these high burn-up samples: (i) a restructuring of the initial grains into smaller sub-grains forming low angle boundaries and with crystal orienta
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Smith, Hannah, Théo Cordara, Clémence Gausse, Sarah E. Pepper, and Claire L. Corkhill. "Oxidative dissolution of Cr-doped UO2 nuclear fuel." npj Materials Degradation 7, no. 1 (2023). http://dx.doi.org/10.1038/s41529-023-00347-4.

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AbstractAlternative UO2 nuclear fuels, incorporating Cr as a dopant, are currently in use in light–water reactors. Dissolution experiments using Cr-doped UO2, performed as a function of Cr content in a simplified groundwater solution and under oxic conditions, established that the addition of Cr to the UO2 matrix systematically reduced the normalised dissolution rate of U at 25 and 40 °C. This effect was most notable under dilute solution conditions, and is the result of galvanic coupling between Cr and U, resulting from the presence of Cr2+ in the UO2 matrix, as corroborated by activation ene
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15

Murphy, Gabriel L., Robert Gericke, Sara Gilson, et al. "Deconvoluting Cr states in Cr-doped UO2 nuclear fuels via bulk and single crystal spectroscopic studies." Nature Communications 14, no. 1 (2023). http://dx.doi.org/10.1038/s41467-023-38109-0.

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AbstractCr-doped UO2 is a leading accident tolerant nuclear fuel where the complexity of Cr chemical states in the bulk material has prevented acquisition of an unequivocal understanding of the redox chemistry and mechanism for incorporation of Cr in the UO2 matrix. To resolve this, we have used electron paramagnetic resonance, high energy resolution fluorescence detection X-ray absorption near energy structure and extended X-ray absorption fine structure spectroscopic measurements to examine Cr-doped UO2 single crystal grains and bulk material. Ambient condition measurements of the single cry
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Kegler, Philip, Stefan Neumeier, Martina Klinkenberg, et al. "Accelerated dissolution of doped UO2-based model systems as analogues for modern spent nuclear fuel under repository conditions." MRS Advances, March 21, 2023. http://dx.doi.org/10.1557/s43580-023-00544-y.

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AbstractSystematic single-effect dissolution studies were carried out on the dissolution behaviour of pure and Cr- or Nd-doped UO2 reference pellets as model materials for spent nuclear fuel with varying doping levels, densities, and grain sizes as well as of industrially produced Cr- and Cr/Nd-doped UO2 pellets. The results were obtained from accelerated static batch dissolution experiments performed under strictly controlled conditions using H2O2 as simulant for radiolytic oxidants formed due to the alpha-irradiation of water. The results indicate that the addition of Cr and the consequentia
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Milena-Pérez, A., L. J. Bonales, N. Rodríguez-Villagra, J. Cobos, and H. Galán. "Raman spectroscopy study of the influence of additives (Cr-, Cr/Al-, and Gd) on UO2 dissolution behavior." MRS Advances, February 4, 2025. https://doi.org/10.1557/s43580-025-01172-4.

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Abstract In this work, Raman spectroscopy (RS) has been used to study the behavior of spent nuclear fuel (SNF) under disposal conditions. In particular, evolutionary Accident-Tolerant Fuels (ATFs) consisting in UO2 doped with Cr and Cr/Al; as well as neutron absorbers (UO2 doped with Gd), has been manufactured and studied. The prepared pellets have been exposed to three different pH leachants (inert media, carbonated media, and young cement water with calcium) for distinct times. RS analyses have been conducted in both the leached and the unleached pellets. The results show that the addition o
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Owen, Megan W., Michael W. D. Cooper, Michael J. D. Rushton, Antoine Claisse, William E. Lee, and Simon C. Middleburgh. "Diffusion in undoped and Cr-doped amorphous UO2." Journal of Nuclear Materials, January 2023, 154270. http://dx.doi.org/10.1016/j.jnucmat.2023.154270.

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Rodríguez-Villagra, N., O. Riba, A. Milena-Pérez, et al. "Dopant effect on the spent fuel matrix dissolution of new advanced fuels: Cr-doped UO2 and Cr/Al-doped UO2." Journal of Nuclear Materials, June 2022, 153880. http://dx.doi.org/10.1016/j.jnucmat.2022.153880.

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20

Smith, Hannah, Luke T. Townsend, Ritesh Mohun, et al. "Cr2+ solid solution in UO2 evidenced by advanced spectroscopy." Communications Chemistry 5, no. 1 (2022). http://dx.doi.org/10.1038/s42004-022-00784-3.

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AbstractAdvanced Cr-doped UO2 fuels are essential for driving safe and efficient generation of nuclear energy. Although widely deployed, little is known about their fundamental chemistry, which is a critical gap for development of new fuel materials and radioactive waste management strategies. Utilising an original approach, we directly evidence the chemistry of Cr(3+)2O3–doped U(4+)O2. Advanced high-flux, high-spectral purity X-ray absorption spectroscopy (XAS), corroborated by diffraction, Raman spectroscopy and high energy resolved fluorescence detection-XAS, is used to establish that Cr2+
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Milena-Pérez, A., L. J. Bonales, N. Rodríguez-Villagra, M. B. Gómez-Mancebo, and H. Galán. "Oxidation of Accident Tolerant Fuels models based on Cr-doped UO2 for the safety of nuclear storage facilities." Journal of Nuclear Materials, May 2023, 154502. http://dx.doi.org/10.1016/j.jnucmat.2023.154502.

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