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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).
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). .
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