Tritium release behavior of beryllium pebbles after neutron irradiation between 523 and 823K

Author:

Vītiņš Aigars,Ķizāne Gunta,Matīss Andris,Pajuste Elīna,Zubkovs Vitālijs

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference14 articles.

1. Development and qualification of functional materials for the EU Test Blanket Modules: Strategy and R&D activities

2. Tritium breeder blankets design and technologies in Europe: Development status of ITER Test Blanket Modules, test & qualification strategy and roadmap towards DEMO

3. Test-element assembly and loading parameters for the in-pile test of HCPB ceramic pebble beds

4. L. Magielsen, J.G. van der Laan, J.H. Fokkens, M.P. Stijkel, In pile behavior of the Pebble bed Assemblies in the HFR, results and first data analyses, in: R. Knitter (Ed.), Proceedings of the 12th International Workshop on Ceramic Breeder Blanket Interactions (CBBI-12), Karlsruhe, Germany, September 16–17, 2004, Wissenschaftliche Berichte FZKA 7078, Forschungszentrum Karlsruhe, December 2004, pp. 183–195.

5. A.V. Fedorov, S. van Til, A.J. Magielsen, M.P. Stijkel, Analysis of tritium retention in beryllium pebbles in EXOTIC, PBA and HIDOBE-01 experiments, J. Nucl. Mater., this issue.

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