Radiological characterization of ceramic materials considered for the HT-DCLL DEMO reactor
Nuclear Materials and Energy（2022）
Abstract
•Radiological characterization of DCLL BB for European DEMO reactor.•Selection of ceramic structure for a High Temperature SMS DCLL BB concept.•Maintenance operations and radioactive waste classification for 17 ceramics.•SiC, TiC and ZrO2 promising options under activation performances.•Theoretical and industrial compositions characterized.
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Key words
Activation,Waste Management,Ceramics,DCLL BB
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