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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
Radial delayed hydride cracking in irradiated Zircaloy-2 cladding: advanced characterization techniques
Colldeweih, A. W., Fagnoni, F., Yetik, O., Zubler, R., Trtik, P., Anghel, C., … Bertsch, J. (2023). Radial delayed hydride cracking in irradiated Zircaloy-2 cladding: advanced characterization techniques. In ASTM special technical publication: Vol. STP 1645. International symposium on zirconium in the nuclear industry (pp. 260-285). https://doi.org/10.1520/STP164520220027
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
Hydrogen diffusion in zirconium cladding alloys with an inner liner as quantified by neutron radiography and nanoindentation
Fagnoni, F., Trtik, P., Wheeler, J. M., Zubler, R., Bertsch, J., & Duarte, L. I. (2023). Hydrogen diffusion in zirconium cladding alloys with an inner liner as quantified by neutron radiography and nanoindentation. Journal of Nuclear Materials, 584, 154574 (12 pp.). https://doi.org/10.1016/j.jnucmat.2023.154574
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
Delayed hydride cracking in Zircaloy-2 with and without liner at various temperatures investigated by high-resolution neutron radiography
Colldeweih, A. W., Fagnoni, F., Trtik, P., Zubler, R., Pouchon, M. A., & Bertsch, J. (2022). Delayed hydride cracking in Zircaloy-2 with and without liner at various temperatures investigated by high-resolution neutron radiography. Journal of Nuclear Materials, 561, 153549 (12 pp.). https://doi.org/10.1016/j.jnucmat.2022.153549
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
Hydrogen diffusion and precipitation under non-uniform stress in duplex zirconium nuclear fuel cladding investigated by high-resolution neutron imaging
Gong, W., Trtik, P., Ma, F., Jia, Y., Li, J., & Bertsch, J. (2022). Hydrogen diffusion and precipitation under non-uniform stress in duplex zirconium nuclear fuel cladding investigated by high-resolution neutron imaging. Journal of Nuclear Materials, 570, 153971 (10 pp.). https://doi.org/10.1016/j.jnucmat.2022.153971
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
Effect of the inner liner on the hydrogen distribution of zircaloy-2 nuclear fuel claddings
Duarte, L. I., Fagnoni, F., Zubler, R., Gong, W., Trtik, P., & Bertsch, J. (2021). Effect of the inner liner on the hydrogen distribution of zircaloy-2 nuclear fuel claddings. Journal of Nuclear Materials, 557, 153284 (6 pp.). https://doi.org/10.1016/j.jnucmat.2021.153284
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.).
 

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