Search Results - "Lainet, M."

Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions by Magni, A., Pizzocri, D., Luzzi, L., Lainet, M., Michel, B.

“…The sodium-cooled fast reactor is among the innovative nuclear technologies selected in the framework of the development of Generation IV concepts, allowing…”
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Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment by Luzzi, L., Barani, T., Boer, B., Del Nevo, A., Lainet, M., Lemehov, S., Magni, A., Marelle, V., Michel, B., Pizzocri, D., Schubert, A., Van Uffelen, P., Bertolus, M.

“…Design and safety assessment of fuel pins for application in innovative Generation IV fast reactors calls for a dedicated nuclear fuel modelling and for the…”
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Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions by Magni, A, Pizzocri, D, Luzzi, L, Lainet, M, Michel, B

“…The sodium-cooled fast reactor is among the innovative nuclear technologies selected in the framework of the development of Generation IV concepts, allowing…”
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Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment by Luzzi, L., Barani, T., Boer, B., Cognini, L., Del Nevo, A., Lainet, M., Lemehov, S., Magni, A., Marelle, V., Michel, B., Pizzocri, D., Schubert, A., Van Uffelen, P., Bertolus, M.

“…The design phase and safety assessment of Generation IV liquid metal-cooled fast reactors calls for the improvement of fuel pin performance codes, in…”
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Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment by Luzzi, L, Barani, T, Boer, B, Cognini, L, Nevo, A. Del, Lainet, M, Lemehov, S, Magni, A, Marelle, V, Michel, B, Pizzocri, D, Schubert, A, Uffelen, P. Van, Bertolus, M

“…The design phase and safety assessment of Generation IV liquid metal-cooled fast reactors calls for the improvement of fuel pin performance codes, in…”
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New recommendation for the thermal conductivity of irradiated (U, Pu)O2 fuels under fast reactor conditions. Comparison with recent experimental data by Bonev, P., Chauvin, N., Staicu, D., Dahms, E., Montagnier, G., Papaioannou, D., Dumas, J-C., Boukhris, I., Viallard, I., Lainet, M., Lamontagne, J., Hanifi, K.

“…New experimental results obtained at the Joint Research Centre in Karlsruhe (JRC-Karlsruhe) within the European Sustainable Nuclear Industrial Initiative Plus…”
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