tIn the breeding areas a significant fraction of the tritium produced is extracted out from the Breeding Zoneby the He gas purging the breeding ceramic in the helium cooled pebble bed (HCPB) blanket concept ortransported in solution by the flowing liquid metal alloy in the helium cooled lead lithium (HCLL) blanketconcept and then extracted outside the blanket box. Tritium produced inside the breeder can enter themetal structures and can be lost by permeation to the environment. It should therefore be kept underclose control throughout the fusion reactor lifetime.In this study the problem of tritium transport in HCPB DEMO blanket has been studied and analysedby means of the computational code FUS-TPC, which has been originally developed to study the tritiumtransport in HCLL blanket and it has the main goal to provide the total tritium losses into the environmentand the tritium inventories inside several HCPB blanket locations (e.g. purge gas and main coolant loops).
|Titolo:||Tritium transport analysis in HCPB DEMO blanket with the FUS-TPC Code|
|Data di pubblicazione:||2013|
|Digital Object Identifier (DOI):||10.1016/j.fusengdes.2013.05.045|
|Appare nelle tipologie:||1.1 Articolo in rivista|
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