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Fabrication and microstructure characterization of inert matrix fuel based on yttria stabilized zirconia
Hellwig, C., Pouchon, M., Restani, R., Ingold, F., & Bart, G. (2005). Fabrication and microstructure characterization of inert matrix fuel based on yttria stabilized zirconia. Journal of Nuclear Materials, 340(2-3), 163-170. https://doi.org/10.1016/j.jnucmat.2004.11.004
Multiscale approach for investigating properties of high temperature materials
Pouchon, M. A., Chen, J., Samaras, M., Tharian, J., & Hoffelner, W. (2005). Multiscale approach for investigating properties of high temperature materials. In GLOBAL 2005: proceedings of the international conference on nuclear energy systems for future generation and global sustainability (p. 274 (5 pp.). Atomic Energy Society of Japan.
Specific heat capacity and Debye temperature of zirconia and its solid solution
Degueldre, C., Tissot, P., Lartigue, H., & Pouchon, M. (2003). Specific heat capacity and Debye temperature of zirconia and its solid solution. Thermochimica Acta, 403(2), 267-273. https://doi.org/10.1016/S0040-6031(03)00060-1
Manufacturing of zirconia microspheres doped with erbia, yttria and ceria by internal gelation process as a part of a cermet fuel
Idemitsu, K., Arima, T., Inagaki, Y., Torikai, S., & Pouchon, M. A. (2003). Manufacturing of zirconia microspheres doped with erbia, yttria and ceria by internal gelation process as a part of a cermet fuel. Journal of Nuclear Materials, 319, 31-36. https://doi.org/10.1016/S0022-3115(03)00130-2
Cermet sphere-pac concept for inert matrix fuel
Pouchon, M. A., Nakamura, M., Hellwig, C., Ingold, F., & Degueldre, C. (2003). Cermet sphere-pac concept for inert matrix fuel. Journal of Nuclear Materials, 319, 37-43. https://doi.org/10.1016/S0022-3115(03)00131-4
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
Development of sphere-pac nuclear fuel behavior analysis code
Nakamura, M., Nakajima, Y., Pouchon, M. A., Sekine, N., & Hellwig, C. (2002). Development of sphere-pac nuclear fuel behavior analysis code. Journal of Nuclear Science and Technology, 39(Suppl. 3), 701-704. https://doi.org/10.1080/00223131.2002.10875563
A mixed ceramic-metal sphere-pac concept
Pouchon, M. A., Nakamura, M., & Hellwig, C. (2002). A mixed ceramic-metal sphere-pac concept. Journal of Nuclear Science and Technology, 39(Suppl. 3), 830-833. https://doi.org/10.1080/00223131.2002.10875597
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
Behaviour of implanted xenon in yttria-stabilized zirconia as inert matrix of a nuclear fuel
Degueldre, C., Pouchon, M., Döbeli, M., Sickafus, K., Hojou, K., Ledergerber, G., & Abolhassani-Dadras, S. (2001). Behaviour of implanted xenon in yttria-stabilized zirconia as inert matrix of a nuclear fuel. Journal of Nuclear Materials, 289(1-2), 115-121. https://doi.org/10.1016/S0022-3115(00)00690-5
Inert matrix fuel for the utilisation of plutonium
Ledergerber, G., Degueldre, C., Heimgartner, P., Pouchon, M. A., & Kasemeyer, U. (2001). Inert matrix fuel for the utilisation of plutonium. Progress in Nuclear Energy, 38(3-4), 301-308. https://doi.org/10.1016/S0149-1970(00)00122-0
Enhanced retention of cesium in yttria stabilised zirconia by co-implantation of iodine
Pouchon, M. A., Degueldre, C., & Döbeli, M. (2001). Enhanced retention of cesium in yttria stabilised zirconia by co-implantation of iodine. Progress in Nuclear Energy, 38(3-4), 275-276. https://doi.org/10.1016/S0149-1970(00)00116-5
Influence of carbonate complexes on the solubility of zirconia: new experimental data
Pouchon, M. A., Curti, E., Degueldre, C., & Tobler, L. (2001). Influence of carbonate complexes on the solubility of zirconia: new experimental data. Progress in Nuclear Energy, 38(3-4), 443-446. https://doi.org/10.1016/S0149-1970(00)00155-4
Preparation of simulated inert matrix fuel with different powders by dry milling method
Lee, Y. W., Kim, H. S., Kim, S. H., Joung, C. Y., Na, S. H., Ledergerber, G., … Burghartz, M. (1999). Preparation of simulated inert matrix fuel with different powders by dry milling method. Journal of Nuclear Materials, 274(1-2), 7-14. https://doi.org/10.1016/S0022-3115(99)00094-X
Behavior of cesium implanted in zirconia based inert matrix fuel
Pouchon, M. A., Döbeli, M., Degueldre, C., & Burghartz, M. (1999). Behavior of cesium implanted in zirconia based inert matrix fuel. Journal of Nuclear Materials, 274(1-2), 61-65. https://doi.org/10.1016/S0022-3115(99)00042-2
Properties of zirconia-based fuels for plutonium utilization in reactors
Pouchon, M. A., Degueldre, C., & Tissot, P. (1999). Properties of zirconia-based fuels for plutonium utilization in reactors. In C. A. Yoelin (Ed.), Transactions of the American Nuclear Society. 1999 winter meeeting (pp. 126-127). American Nuclear Society (ANS).
Retention of iodine in yttria stabilized zirconia
Pouchon, M. A., Döbeli, M., & Degueldre, C. (1999). Retention of iodine in yttria stabilized zirconia. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 148(1-4), 783-786. https://doi.org/10.1016/S0168-583X(98)00885-4
Determination of the thermal conductivity in zirconia based inert matrix nuclear fuel by oscillating differential scanning calorimetry and laser flash
Pouchon, M. A., Degueldre, C., & Tissot, P. (1998). Determination of the thermal conductivity in zirconia based inert matrix nuclear fuel by oscillating differential scanning calorimetry and laser flash. Thermochimica Acta, 323(1-2), 109-121. https://doi.org/10.1016/S0040-6031(98)00504-8