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Towards an improved understanding of the mechanisms involved in the increased hydrogen uptake and corrosion at high burnups in zirconium based claddings
Abolhassani, S., Baris, A., Grabherr, R., Hawes, J., Colldeweih, A., Vanta, R., … Limbäck, M. (2021). Towards an improved understanding of the mechanisms involved in the increased hydrogen uptake and corrosion at high burnups in zirconium based claddings. In A. T. Motta & S. K. Yagnik (Eds.), ASTM International: selected technical papers: Vol. STP1622. Zirconium in the nuclear industry: 19th international symposium (pp. 435-466). https://doi.org/10.1520/STP162220190052
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
Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels
Chollet, M., Krsjak, V., Cozzo, C., & Bertsch, J. (2017). Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels. EPJ Nuclear Sciences and Technologies, 3, 3 (5 pp.). https://doi.org/10.1051/epjn/2016040
Quantifying the stress field of hydride precipitation by mu-XRD tomography
Chollet, M., Gong, W., Ferreira Sanchez, D., Samson, V. A., & Bertsch, J. (2017). Quantifying the stress field of hydride precipitation by mu-XRD tomography. Presented at the Water reactor fuel performance meeting 2017 (WRFPM 2017). Jeju, Korea.
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
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
Neptunium characterization in uranium dioxide fuel: combining a XAFS and a thermodynamic approach
Chollet, M., Martin, P., Degueldre, C., Poonoosamy, J., Belin, R. C., & Hennig, C. (2016). Neptunium characterization in uranium dioxide fuel: combining a XAFS and a thermodynamic approach. Journal of Alloys and Compounds, 662, 448-454. https://doi.org/10.1016/j.jallcom.2015.12.005
Synchrotron XRD analysis of irradiated UO<sub>2</sub> 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.
Kinetics of the olivine-ringwoodite transformation and seismic attenuation in the Earth's mantle transition zone
Perrillat, J. P., Chollet, M., Durand, S., van de Moortèle, B., Chambat, F., Mezouar, M., & Daniel, I. (2016). Kinetics of the olivine-ringwoodite transformation and seismic attenuation in the Earth's mantle transition zone. Earth and Planetary Sciences Letters, 433, 360-369. https://doi.org/10.1016/j.epsl.2015.11.013
Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels
Chollet, M., Krsjak, V., Cozzo, C., & Bertsch, J. (2015). Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels. In TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 1 (pp. 502-509). European Nuclear Society.
The melting behaviour of uranium/neptunium mixed oxides
Chollet, M., Prieur, D., Böhler, R., Belin, R., & Manara, D. (2015). The melting behaviour of uranium/neptunium mixed oxides. The Journal of Chemical Thermodynamics, 89, 27-34. https://doi.org/10.1016/j.jct.2015.04.031