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Hydrogen enhanced localized plasticity in zirconium as observed by digital image correlation
Fagnoni, F., Kursun, E. .C., Busi, M., Konarski, P., Yetik, O., Spolenak, R., … Duarte, L. I. (2024). Hydrogen enhanced localized plasticity in zirconium as observed by digital image correlation. Journal of Nuclear Materials, 590, 154873 (10 pp.). https://doi.org/10.1016/j.jnucmat.2023.154873
Zirconium hydride phase mapping in Zircaloy-2 cladding after delayed hydride cracking
Colldeweih, A. W., Makowska, M. G., Tabai, O., Sanchez, D. F., & Bertsch, J. (2023). Zirconium hydride phase mapping in Zircaloy-2 cladding after delayed hydride cracking. Materialia, 27, 101689 (10 pp.). https://doi.org/10.1016/j.mtla.2023.101689
Mechanical behavior of Zircaloy-4 in the presence of hydrogen in solid solution at elevated temperatures
Fagnoni, F., Colldeweih, A. W., Binato, S., Wheeler, J. M., Spolenak, R., Wolff, M., … Duarte, L. I. (2023). Mechanical behavior of Zircaloy-4 in the presence of hydrogen in solid solution at elevated temperatures. In ASTM special technical publication: Vol. STP 1645. International symposium on zirconium in the nuclear industry (pp. 218-235). https://doi.org/10.1520/STP164520220019
Insights into the interfacial speciation of Ni in the corrosion layer of high burnup Zircaloy-2 cladding: a combined XRD, XAS, and LFDFT study
Kuri, G., Ramanantoanina, H., Bhattacharya, S., Bertsch, J., & Martin, M. (2023). Insights into the interfacial speciation of Ni in the corrosion layer of high burnup Zircaloy-2 cladding: a combined XRD, XAS, and LFDFT study. Corrosion Science, 215, 111024 (13 pp.). https://doi.org/10.1016/j.corsci.2023.111024
Atomic-scale insights into structural distortions in irradiated UO<sub>2</sub> at an intermediate burnup around 50 MWd/kgU
Bhattacharya, S., Kuri, G., Martin, M., Bertsch, J., & Pouchon, M. A. (2022). Atomic-scale insights into structural distortions in irradiated UO2 at an intermediate burnup around 50 MWd/kgU. In Proceedings of TopFuel 2022 light water reactor fuel performance conference (pp. 278-285). https://doi.org/10.13182/TopFuel22-38929
Effect of temperature and hydrogen concentration on the threshold stress intensity factor of radial delayed hydride cracking in fuel cladding
Colldeweih, A. W., & Bertsch, J. (2022). Effect of temperature and hydrogen concentration on the threshold stress intensity factor of radial delayed hydride cracking in fuel cladding. Journal of Nuclear Materials, 565, 153737 (11 pp.). https://doi.org/10.1016/j.jnucmat.2022.153737
A novel method for radial hydride analysis in zirconium alloys: HAPPy
Maric, M., Thomas, R., Nunez-Iglesias, J., Atkinson, M., Bertsch, J., Frankel, P., … Shanthraj, P. (2022). A novel method for radial hydride analysis in zirconium alloys: HAPPy. Journal of Nuclear Materials, 559, 153442 (14 pp.). https://doi.org/10.1016/j.jnucmat.2021.153442
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
Effect of the inner liner on radial delayed hydride cracking
Colldeweih, A. W., Fagnoni, F., Pouchon, M. A., Bertsch, J., & Trtik, P. (2021). Effect of the inner liner on radial delayed hydride cracking. In TopFuel2021 (p. (6 pp.). European Nuclear Society.
Quantifying the benefits of the reduced oxidation kinetics in chromium-coated cladding: a parametric study
Cozzo, C., Lind, T., Bertsch, J., Nichenko, S., & Girardin, G. (2021). Quantifying the benefits of the reduced oxidation kinetics in chromium-coated cladding: a parametric study. In C. Vázquez-Rodriguez, A. Jiménez Carrascosa, S. Estevez Albuja, & L. F. Duran Vinuesa (Eds.), Book of Proceedings. European nuclear young generation forum 2021 (pp. 245-248). European Nuclear Young Generation Forum.
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
Neutron radiography imaging: a tool for determination of hydrogen distribution in unirradiated and irradiated fuel claddings
Duarte, L. I., Yetik, O., Fagnoni, F., Colldeweih, A., Zubler, R., Bertsch, J., & Trtik, P. (2021). Neutron radiography imaging: a tool for determination of hydrogen distribution in unirradiated and irradiated fuel claddings. In TopFuel2021 (p. (10 pp.). European Nuclear Society.
Elevated temperature nanoindentation of Zry-4 in the presence of hydrogen in solid solution
Fagnoni, F., Duarte, L. I., Bertsch, J., & Wheeler, J. M. (2021). Elevated temperature nanoindentation of Zry-4 in the presence of hydrogen in solid solution. In TopFuel2021 (p. (8 pp.). European Nuclear Society.
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.).
Influence of scattering correction on quantitative hydrogen analysis of fuel claddings using high resolution neutron radiography
Yetik, O., Duarte, L. I., Fagnoni, F., Colldeweih, A., Zubler, R., Pouchon, M. A., … Trtik, P. (2021). Influence of scattering correction on quantitative hydrogen analysis of fuel claddings using high resolution neutron radiography. In TopFuel2021 (p. (10 pp.). European Nuclear Society.
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
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).
Study of electronic structure in the L-edge spectroscopy of actinide materials: UO&lt;sub&gt;2&lt;/sub&gt; 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
 

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