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Post-irradiation examinations of SINQ Target-11
Dai, Y., Boutellier, V., Grabherr, R., Urech, A., Blau, B., Welte, J., … Wohlmuther, M. (2021). Post-irradiation examinations of SINQ Target-11. In K. Kikuchi (Ed.), Materials science forum: Vol. 1024. Spallation materials technology (pp. 41-52). https://doi.org/10.4028/www.scientific.net/MSF.1024.41
Study of electronic structure in the L-edge spectroscopy of actinide materials: UO<sub>2</sub> as an example
Ramanantoanina, H., Kuri, G., Martin, M., & Bertsch, J. (2019). Study of electronic structure in the L-edge spectroscopy of actinide materials: UO2 as an example. Physical Chemistry Chemical Physics, 21(15), 7789-7801. https://doi.org/10.1039/c9cp01021a
Chemical state and atomic scale environment of nickel in the corrosion layer of irradiated Zircaloy-2 at a burn-up around 45 MWd/kg
Kuri, G., Ramanantoanina, H., Bertsch, J., Martin, M., & Panas, I. (2018). Chemical state and atomic scale environment of nickel in the corrosion layer of irradiated Zircaloy-2 at a burn-up around 45 MWd/kg. Corrosion Science, 143, 200-211. https://doi.org/10.1016/j.corsci.2018.08.032
Analysis of the U L<sub>3</sub>-edge X-ray absorption spectra in UO<sub>2</sub> using molecular dynamics simulations
Bocharov, D., Chollet, M., Krack, M., Bertsch, J., Grolimund, D., Martin, M., … Kotomin, E. (2017). Analysis of the U L3-edge X-ray absorption spectra in UO2 using molecular dynamics simulations. Progress in Nuclear Energy, 94, 187-193. https://doi.org/10.1016/j.pnucene.2016.07.017
New insights in the fuel grain subdivision during in-plant irradiation up to high burn-up
Chollet, M., Cozzo, C., Bertsch, J., Martin, M., Grolimund, D., & Samson, V. A. (2017). New insights in the fuel grain subdivision during in-plant irradiation up to high burn-up (p. (9 pp.). Presented at the Water reactor fuel performance meeting 2017 (WRFPM 2017). .
Synchrotron X-ray diffraction investigations on strains in the oxide layer of an irradiated Zircaloy fuel cladding
Chollet, M., Valance, S., Abolhassani, S., Stein, G., Grolimund, D., Martin, M., & Bertsch, J. (2017). Synchrotron X-ray diffraction investigations on strains in the oxide layer of an irradiated Zircaloy fuel cladding. Journal of Nuclear Materials, 488, 181-190. https://doi.org/10.1016/j.jnucmat.2017.03.010
Behavior of solute Ni in the corrosion layer of irradiated Zircaloy-2 cladding: a hydrogen uptake perspective
Kuri, G., Ramanantoanina, H., Martin, M., & Bertsch, J. (2017). Behavior of solute Ni in the corrosion layer of irradiated Zircaloy-2 cladding: a hydrogen uptake perspective. Presented at the Water reactor fuel performance meeting 2017 (WRFPM 2017). Jeju, Korea.
Interpretation of the U L<sub>3</sub>-edge EXAFS in uranium dioxide using molecular dynamics and density functional theory simulations
Bocharov, D., Chollet, M., Krack, M., Bertsch, J., Grolimund, D., Martin, M., … Kotomin, E. (2016). Interpretation of the U L3-edge EXAFS in uranium dioxide using molecular dynamics and density functional theory simulations. In Journal of physics: conference series: Vol. 712. 16th international conference on X-ray absorption fine structure (XAFS16) (p. 12091 (4 pp.). https://doi.org/10.1088/1742-6596/712/1/012091
Synchrotron XRD analysis of irradiated UO&lt;sub&gt;2&lt;/sub&gt; fuel at various burn-up
Chollet, M., Kuri, G., Martin, M., Bertsch, J., & Grolimund, D. (2016). Synchrotron XRD analysis of irradiated UO2 fuel at various burn-up. In Top Fuel 2016. LWR fuels with enhanced safety and performance (pp. 339-346). American Nuclear Society.
Post irradiation examination of nuclear fuel: toward a complete analysis
Degueldre, C., Bertsch, J., & Martin, M. (2016). Post irradiation examination of nuclear fuel: toward a complete analysis. Progress in Nuclear Energy, 92, 242-253. https://doi.org/10.1016/j.pnucene.2016.03.025
On the condition of UO&lt;sub&gt;2&lt;/sub&gt; nuclear fuel irradiated in a PWR to a burn-up in excess of 110 MWd/kgHM
Restani, R., Horvath, M., Goll, W., Bertsch, J., Gavillet, D., Hermann, A., … Walker, C. T. (2016). On the condition of UO2 nuclear fuel irradiated in a PWR to a burn-up in excess of 110 MWd/kgHM. Journal of Nuclear Materials, 481, 88-100. https://doi.org/10.1016/j.jnucmat.2016.08.023
Corrosion and hydrogen uptake in zirconium claddings irradiated in light water reactors
Abolhassani, S., Bart, G., Bertsch, J., Grosse, M., Hallstadius, L., Hermann, A., … Wiese, H. (2015). Corrosion and hydrogen uptake in zirconium claddings irradiated in light water reactors. In R. J. Comstock & P. Barbéris (Eds.), Vol. STP1543. Zirconium in the nuclear industry. 17th international symposium (pp. 540-573). https://doi.org/10.1520/STP154320130007
Evolution of the atomic-scale structure from a pristine to high burn-up UO&lt;sub&gt;2&lt;/sub&gt; fuel by X-ray absorption spectroscopy
Chollet, M., Bertsch, J., Grolimund, D., & Martin, M. (2015). Evolution of the atomic-scale structure from a pristine to high burn-up UO2 fuel by X-ray absorption spectroscopy. Presented at the 2015 E-MRS spring meeting.
Theoretical modelling of pristine and chromium-doped UO<sub>2</sub>
Chollet, M., Krack, M., Kuzmin, A., Bertsch, J., Grolimund, D., & Martin, M. (2015). Theoretical modelling of pristine and chromium-doped UO2. Presented at the E-MRS 2015. Lille, France.
Selenium redox speciation and coordination in high-burnup UO&lt;sub&gt;2&lt;/sub&gt; fuel: consequences for the release of &lt;sup&gt;79&lt;/sup&gt;Se in a deep underground repository
Curti, E., Froideval-Zumbiehl, A., Günther-Leopold, I., Martin, M., Bullemer, A., Linder, H., … Grolimund, D. (2014). Selenium redox speciation and coordination in high-burnup UO2 fuel: consequences for the release of 79Se in a deep underground repository. Journal of Nuclear Materials, 453(1-3), 98-106. https://doi.org/10.1016/j.jnucmat.2014.07.003
X-ray fluorescence and absorption analysis of krypton in irradiated nuclear fuel
Degueldre, C., Mieszczynski, C., Borca, C., Grolimund, D., Martin, M., & Bertsch, J. (2014). X-ray fluorescence and absorption analysis of krypton in irradiated nuclear fuel. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 336, 116-122. https://doi.org/10.1016/j.nimb.2014.06.021
Local atomic structure of chromium bearing precipitates in chromia doped uranium dioxide investigated by combined micro-beam X-ray diffraction and absorption spectroscopy
Kuri, G., Mieszczynski, C., Martin, M., Bertsch, J., Borca, C. N., & Delafoy, C. (2014). Local atomic structure of chromium bearing precipitates in chromia doped uranium dioxide investigated by combined micro-beam X-ray diffraction and absorption spectroscopy. Journal of Nuclear Materials, 449(1-3), 158-167. https://doi.org/10.1016/j.jnucmat.2014.03.017
Microbeam X-ray diffraction to study radiation damage in irradiated uranium dioxide nuclear fuel
Kuri, G., Martin, M., & Bertsch, J. (2014). Microbeam X-ray diffraction to study radiation damage in irradiated uranium dioxide nuclear fuel. In H. Ishibashii (Ed.), Proceedings of 2014 water reactor fuel performance meeting, top fuel, LWR fuel performance meeting (WRFPM 2014) (p. 100043). Sine nomine.
Irradiation effects and micro-structural changes in large grain uranium dioxide fuel investigated by micro-beam X-ray diffraction
Mieszczynski, C., Kuri, G., Degueldre, C., Martin, M., Bertsch, J., Borca, C. N., … Simoni, E. (2014). Irradiation effects and micro-structural changes in large grain uranium dioxide fuel investigated by micro-beam X-ray diffraction. Journal of Nuclear Materials, 444(1-3), 274-282. https://doi.org/10.1016/j.jnucmat.2013.09.054
Microbeam x-ray absorption spectroscopy study of chromium in large-grain uranium dioxide fuel
Mieszczynski, C., Kuri, G., Bertsch, J., Martin, M., Borca, C. N., Delafoy, C., & Simoni, E. (2014). Microbeam x-ray absorption spectroscopy study of chromium in large-grain uranium dioxide fuel. Journal of Physics: Condensed Matter, 26(35), 355009 (8 pp.). https://doi.org/10.1088/0953-8984/26/35/355009