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|WP7 ||CIEMAT ||Tritium transport predictive modelling tools for Breeding Blanket design analyses and system modelling<ref>P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 & 15 Sept. 2011) Poster S. 1-055 and 3-051 | |WP7 ||CIEMAT ||Tritium transport predictive modelling tools for Breeding Blanket design analyses and system modelling<ref>P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 & 15 Sept. 2011) Poster S. 1-055 and 3-051 | ||
</ref><ref>P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)</ref><ref>P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT | </ref><ref>P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)</ref><ref>P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html</ref> | ||
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|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials <ref>G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html </ref><ref>E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) | |WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials <ref>G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html </ref><ref>E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) </ref> | ||
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