| 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 |