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Relevant bibliographies by topics / UO2 Cr doped

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Journal articles

Academic literature on the topic 'UO2 Cr doped'

Author: Grafiati

Published: 1 March 2025

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Journal articles on the topic "UO2 Cr doped"

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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2

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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3

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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4

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&amp;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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5

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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6

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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7

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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8

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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9

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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10

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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