Removing Tritium and Other Impurities During Industrial Recycling of Beryllium from a Fusion Reactor

作者: Kris Dylst , John Seghers , Frank Druyts , Johan Braet

DOI: 10.13182/FST08-A1798

关键词: BerylliumTritiumImpurityNeutronMaterials sciencePowder metallurgyChlorineFusion powerMetallurgyBeryllium chloride

摘要: Recycling beryllium used in a fusion reactor might be good way to overcome problems related the disposal of neutron irradiated beryllium. The critical issues for recycling first wall are presence tritium and (transuranic) impurities. High temperature annealing seems most promising technique detritiation. Purification detritiated can achieved by chlorination subsequent reduction chloride highly pure metallic After that, re-fabricated into tiles via powder metallurgy which is already mature industrial practice. This paper outlines path define experimental needs tackles detritiation purification chlorine route.

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