| Irradiation and post-irradiation examination of uranium-free nitride fuel
Hania, P. R., Klaassen, F. C., Wernli, B., Streit, M., Restani, R., Ingold, F., … Wallenius, J. (2015). Irradiation and post-irradiation examination of uranium-free nitride fuel. Journal of Nuclear Materials, 466, 597-605. https://doi.org/10.1016/j.jnucmat.2015.08.054 |
| Thermodynamic modelling of molybdenum behaviour in chloride molten salt
Nichenko, S., & Streit, M. (2015). Thermodynamic modelling of molybdenum behaviour in chloride molten salt. In TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 1 (pp. 222-232). European Nuclear Society. |
| Platinum deposition on a boiling stainless steel surface (simulating a fuel rod)
Veleva, L., Grundler, P. V., Streit, M., & Ritter, S. (2015). Platinum deposition on a boiling stainless steel surface (simulating a fuel rod). In TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 3 (pp. 262-271). European Nuclear Society. |
| Inert matrix fuel behaviour in test irradiations
Hellwig, C., Streit, M., Blair, P., Tverberg, T., Klaassen, F. C., Schram, R. P. C., … Yamashita, T. (2006). Inert matrix fuel behaviour in test irradiations. Journal of Nuclear Materials, 352(1-3), 291-299. https://doi.org/10.1016/j.jnucmat.2006.02.065 |
| Inert matrix and thoria fuel irradiation at an international research reactor
Streit, M., Tverberg, T., Wiesenack, W., & Vettraino, F. (2006). Inert matrix and thoria fuel irradiation at an international research reactor. Journal of Nuclear Materials, 352(1-3), 263-267. https://doi.org/10.1016/j.jnucmat.2006.02.063 |
| Yttrium stabilised zirconia inert matrix fuel irradiation at an international research reactor
Streit, M., Wiesenack, W., Tverberg, T., Hellwig, C., & Oberländer, B. C. (2006). Yttrium stabilised zirconia inert matrix fuel irradiation at an international research reactor. Journal of Nuclear Materials, 352(1-3), 349-356. https://doi.org/10.1016/j.jnucmat.2006.02.067 |
| Experimental assessment of thermophysical properties of (Pu,Zr)N
Basini, V., Ottaviani, J. P., Richaud, J. C., Streit, M., & Ingold, F. (2005). Experimental assessment of thermophysical properties of (Pu,Zr)N. Journal of Nuclear Materials, 344(1-3), 186-190. https://doi.org/10.1016/j.jnucmat.2005.04.040 |
| Nitrides as a nuclear fuel option
Streit, M., & Ingold, F. (2005). Nitrides as a nuclear fuel option. Journal of the European Ceramic Society, 25(12), 2687-2692. https://doi.org/10.1016/j.jeurceramsoc.2005.03.181 |
| Thermo-chemical modelling of uranium-free nitride fuels
Jolkkonen, M., Streit, M., & Wallenius, J. (2004). Thermo-chemical modelling of uranium-free nitride fuels. Journal of Nuclear Science and Technology, 41(4), 457-465. https://doi.org/10.1080/18811248.2004.9715508 |
| Fabrication and characterisation of (Pu,Zr)N fuels
Streit, M. (2004). Fabrication and characterisation of (Pu,Zr)N fuels [Doctoral dissertation, ETH Zurich]. https://doi.org/10.3929/ethz-a-004674329 |
| Zirconium nitride as inert matrix for fast systems
Streit, M., Ingold, F., Pouchon, M., Gauckler, L. J., & Ottaviani, J. P. (2003). Zirconium nitride as inert matrix for fast systems. Journal of Nuclear Materials, 319, 51-58. https://doi.org/10.1016/S0022-3115(03)00133-8 |
| 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 |
| (Pu,Zr)N annular fuel pellets shaped by direct coagulation casting
Streit, M., Ingold, F., Gauckler, L. J., & Ottaviani, J. P. (2002). (Pu,Zr)N annular fuel pellets shaped by direct coagulation casting. Journal of Nuclear Science and Technology, 39(Suppl. 3), 741-744. https://doi.org/10.1080/00223131.2002.10875573 |
| Analysis of porous features in zirconia based inert matrix, impact on the material qualification
Degueldre, C., Pouchon, M., Streit, M., Zaharko, O., & Di Michiel, M. (2001). Analysis of porous features in zirconia based inert matrix, impact on the material qualification. Progress in Nuclear Energy, 38(3-4), 241-246. https://doi.org/10.1016/S0149-1970(00)00108-6 |
| Direct coagulation casting - a new shaping method in nuclear field
Streit, M., Ingold, F., Gauckler, L. J., & Ottaviani, J. P. (2001). Direct coagulation casting - a new shaping method in nuclear field. In French national radioactive waste management agency (ANDRA) (Ed.), Global 2001. Proceedings / international conference on "Back-end of the fuel cycle: from research to solutions", Paris-France, September 9-13, 2001 (p. (8 pp.). sine nomine. |
