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Tritium transport analysis in HCPB DEMO blanket with the FUS-TPC Code (KIT Scientific Reports ; 7642)

Franza, Fabrizio

In thermonuclear fusion reactors, the fuel is an high temperature deuterium-tritium plasma, in which tritium is bred by lithium isotopes present inside solid ceramic breeder (e.g. Li-Orthosilicate) or inside liquid eutectic alloys (e.g. Pb-16Li alloy). 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 owing alloy in the Helium Cooled Lead Lithium (HCLL) blanket concept.
Tritium produced in the breeding blanket by neutrons interacting with lithium nuclei can enter the metal structures, and can be lost by permeation to the environment. Tritium in metallic components should therefore be kept under close control throughout the fusion reactor lifetime, bearing in mind the risk of accidents and the need for maintenance.
In this study the problem of tritium transport in HCPB DEMO blanket from the generation inside the solid breeder to the release into the environment has been studied and analyzed by means of the computational code FUS-TPC (Fusion Devoted-Tritium Permeation Code). ... mehr

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Volltext §
DOI: 10.5445/KSP/1000034375
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Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Forschungsbericht
Jahr 2013
Sprache Englisch
Identifikator ISBN: 978-3-7315-0012-4
KITopen-ID: 1000034375
Reportnummer: KIT-SR 7642
HGF-Programm 31.40.01 (POF II, LK 01)
Verlag KIT Scientific Publishing, Karlsruhe
Umfang X, 74 S.
Schlagworte Tritium, Permeation, DEMO, HCPB, Blanket
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