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Tritium transport analysis of HCPB blanket for CFETR
Fusion Engineering and Design, 2016Abstract Based on the HCPB (Helium-Cooled Pebble Bed) blanket of CFETR (Chinese Fusion Engineering Testing Reactor), a more detailed tritium cycle model of HCPB blanket was developed by modeling the breeding parts inside the blanket separately. Utilizing the detailed model, tritium transport analysis of HCPB blanket was carried out.
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RAMI analysis for DEMO HCPB blanket concept cooling system
Fusion Engineering and Design, 2015Abstract A preliminary RAMI (reliability, availability, maintainability and inspectability) assessment for the HCPB (helium cooled pebble bed) blanket cooling system based on currently available design for DEMO fusion power plant is presented. The following sub-systems were considered in the analysis: blanket modules, primary cooling loop including ...
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Tritium transport analysis in HCPB DEMO blanket with the FUS-TPC code
Fusion Engineering and Design, 2013Abstract In the breeding areas a significant fraction of the tritium produced is extracted out from the Breeding Zone by the He gas purging the breeding ceramic in the helium cooled pebble bed (HCPB) blanket concept or transported in solution by the flowing liquid metal alloy in the helium cooled lead lithium (HCLL) blanket concept and then extracted
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Tritium Behavior in HCPB Breeder Blanket Unit: Modeling and Experiments
Fusion Science and Technology, 2017AbstractTritium behavior in a breeding blanket is a key design issue because of its impact on safety and fuel self-sufficiency best performance. Considering the difficulty in handling and its high cost, it is intended to prepare a simulation tool for tritium transport in the HCPB (Helium Cooled Pebble Bed) breeder blanket unit concept. The objective of
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