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Transmission electron microscopy examinations of metal-oxide interface of zirconium-based alloys irradiated in Halden reactor-IFA-638
Abolhassani, S., Proff, C., Veleva, L., Karlsen, T. M., Bennett, P., Oberländer, B., … Garde, A. M. (2018). Transmission electron microscopy examinations of metal-oxide interface of zirconium-based alloys irradiated in Halden reactor-IFA-638. In R. J. Comstock & A. T. Motta (Eds.), ASTM special technical publication: Vol. STP1597. Zirconium in the nuclear industry: 18th international symposium (pp. 614-644). https://doi.org/10.1520/STP159720160039
Corrosion and hydrogen uptake in zirconium claddings irradiated in light water reactors
Abolhassani, S., Bart, G., Bertsch, J., Grosse, M., Hallstadius, L., Hermann, A., … Wiese, H. (2015). Corrosion and hydrogen uptake in zirconium claddings irradiated in light water reactors. In R. J. Comstock & P. Barbéris (Eds.), Vol. STP1543. Zirconium in the nuclear industry. 17th international symposium (pp. 540-573). https://doi.org/10.1520/STP154320130007
Oxidation behaviour of zirconium alloys and their precipitates - a mechanistic study
Proff, C., Abolhassani, S., & Lemaignan, C. (2013). Oxidation behaviour of zirconium alloys and their precipitates - a mechanistic study. Journal of Nuclear Materials, 432(1-3), 222-238. https://doi.org/10.1016/j.jnucmat.2012.06.026