Active Filters

  • (-) PSI Authors = Bertsch, Johannes
Search Results 1 - 20 of 60
Select Page
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
NEURAP - a dedicated neutron-imaging facility for highly radioactive samples
Lehmann, E., Thomsen, K., Strobl, M., Trtik, P., Bertsch, J., & Dai, Y. (2021). NEURAP - a dedicated neutron-imaging facility for highly radioactive samples. Journal of Imaging, 7(3), 57 (14 pp.). https://doi.org/10.3390/jimaging7030057
Materials and corrosion issues in the primary coolant circuit of boiling water reactors
Seifert, H. P., & Bertsch, J. (2021). Materials and corrosion issues in the primary coolant circuit of boiling water reactors. Techniques de l'ingénieur, EBN 3 762 (30 pp.).
High temperature nanoindentation of hydrogenated Zry-4
Fagnoni, F., Duarte, L. I., Wheeler, J. M., & Bertsch, J. (2020). High temperature nanoindentation of hydrogenated Zry-4. Presented at the NuMat 2020. Ghent, Belgium.
The effect of (Si, Cr, Fe, Ni, Nb, Sn) and monovacancy on hydrogen incorporation into Zr (0001): ab initio insights
Mebtouche, F., Zergoug, T., El Hak Abaidia, S., Bertsch, J., Seddik Kebaili, A. B., & Nedjar, A. (2020). The effect of (Si, Cr, Fe, Ni, Nb, Sn) and monovacancy on hydrogen incorporation into Zr (0001): ab initio insights. Computational and Theoretical Chemistry, 1178, 112781 (9 pp.). https://doi.org/10.1016/j.comptc.2020.112781
Sample container for high-resolution neutron imaging of spent nuclear fuel cladding sections
Trtik, P., Zubler, R., Gong, W., Grabherr, R., Bertsch, J., & Duarte, L. I. (2020). Sample container for high-resolution neutron imaging of spent nuclear fuel cladding sections. Review of Scientific Instruments, 91(5), 056103 (3 pp.). https://doi.org/10.1063/1.5143226
Influence of cracking direction on fracture mechanics during DHC of Zircaloy-2 cladding
Colldeweih, A. W., Gong, W., Zubler, R., Bertsch, J., & Trtik, P. (2019). Influence of cracking direction on fracture mechanics during DHC of Zircaloy-2 cladding. In Global/top fuel 2019 (pp. 240-245). American Nuclear Society (ANS).
Hydride characterization in Zircaloy-2 liner cladding after C-shaped ring compression tests
Duarte, L. I., Fagnoni, F., Zubler, R., Gong, W., Trtik, P., & Bertsch, J. (2019). Hydride characterization in Zircaloy-2 liner cladding after C-shaped ring compression tests. In Global/top fuel 2019 (pp. 166-172). American Nuclear Society (ANS).
Hydrides in irradiated liner cladding - local and in-depth concentration determination by neutron radiography
Duarte, L. I., Fagnoni, F., Zubler, R., Gong, W., Trtik, P., & Bertsch, J. (2019). Hydrides in irradiated liner cladding - local and in-depth concentration determination by neutron radiography. In Global/top fuel 2019 (pp. 928-932). American Nuclear Society (ANS).
Anisotropic influence of hydrides on Zircaloy fatigue
Gong, W., Mille, M., Zubler, R., & Bertsch, J. (2019). Anisotropic influence of hydrides on Zircaloy fatigue. In Global/top fuel 2019 (pp. 334-343). American Nuclear Society (ANS).
Hydride reorientation and redistribution under non-uniform stress
Gong, W., Trtik, P., Zubler, R., & Bertsch, J. (2019). Hydride reorientation and redistribution under non-uniform stress. In Global/top fuel 2019 (pp. 354-359). American Nuclear Society (ANS).
Hydrogen diffusion and precipitation in duplex zirconium nuclear fuel cladding quantified by high-resolution neutron imaging
Gong, W., Trtik, P., Colldeweih, A. W., Duarte, L. I., Grosse, M., Lehmann, E., & Bertsch, J. (2019). Hydrogen diffusion and precipitation in duplex zirconium nuclear fuel cladding quantified by high-resolution neutron imaging. Journal of Nuclear Materials, 526, 151757 (13 pp.). https://doi.org/10.1016/j.jnucmat.2019.151757
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
Hydrogen diffusion under stress in Zircaloy: high-resolution neutron radiography and finite element modeling
Gong, W., Trtik, P., Valance, S., & Bertsch, J. (2018). Hydrogen diffusion under stress in Zircaloy: high-resolution neutron radiography and finite element modeling. Journal of Nuclear Materials, 508, 459-464. https://doi.org/10.1016/j.jnucmat.2018.05.079
Neutronenradiographie- und -tomographieuntersuchungen der Wasserstoffdiffusion und -verteilung in Zirkonium. Investigations of the hydrogen diffusion and distribution in Zirconium by means of neutron imaging
Grosse, M., Santisteban, J. R., Bertsch, J., Schillinger, B., Kaestner, A., Daymond, M. R., & Kardjilov, N. (2018). Neutronenradiographie- und -tomographieuntersuchungen der Wasserstoffdiffusion und -verteilung in Zirkonium. Investigations of the hydrogen diffusion and distribution in Zirconium by means of neutron imaging. Kerntechnik, 83(6), 495-501. https://doi.org/10.3139/124.110946
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). .
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.