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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
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
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 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.
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.
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).
Hybrides impact on zircaloy fatigue properites
Gong, W., Brenin, A., Zubler, R., & Bertsch, J. (2017). Hybrides impact on zircaloy fatigue properites (p. (9 pp.). Presented at the 2017 water reactor fuel performance meeting (WRFPM 2017). .
Stress-induced hydrogen redistribution in zircaloy measured by high-resolution neutron imaging
Gong, W., Trtik, P., Zubler, R., & Bertsch, J. (2017). Stress-induced hydrogen redistribution in zircaloy measured by high-resolution neutron imaging (p. (8 pp.). Presented at the 2017 water reactor fuel performance meeting (WRFPM 2017). .
Hydrides re-orientation and metallography analysis of five cycles irradiated fuel cladding samples
Zubler, R., Valance, S., Bertsch, J., & Urech, A. (2012). Hydrides re-orientation and metallography analysis of five cycles irradiated fuel cladding samples (p. (10 pp.). Presented at the 49th conference on hot laboratories and remote handling (HOTLAB 2012). .
Crack resistance curve determination of Zircaloy-4 cladding
Bertsch, J., Alam, A., & Zubler, R. (2009). Crack resistance curve determination of Zircaloy-4 cladding. (PSI Bericht, Report No.: 09-04). Paul Scherrer Institut.
Fabrication of neptunium containing MOX fuel microspheres
Ingold, F., Wichser, J., Zubler, R., Streit, M., Kopajtic, Z., & Kono, S. (2002). Fabrication of neptunium containing MOX fuel microspheres. Journal of Nuclear Science and Technology, 39(Suppl. 3), 717-720. https://doi.org/10.1080/00223131.2002.10875567