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|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials | |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> | ||
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