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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).
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.
Neutron radiation hardness of vacuum compatible two-component adhesives
Bertsch, J., Goeltl, L., Kirch, K., Lauss, B., & Zubler, R. (2009). Neutron radiation hardness of vacuum compatible two-component adhesives. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 602(2), 552-556. https://doi.org/10.1016/j.nima.2009.01.020
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