Tritium control modelling for a helium cooled lithium-lead blanket of a fusion power reactor

Fusion Engineering and Design

Volumn 81 A, Issue 1-4, 2006, Pages 753-762

  Farabolini, W ^a   Ciampichetti, A ^b   Dabbene, F ^a   Futterer M A ^c   Giancarli, L ^a   Laffont, G ^d   Puma, A Li ^a   Raboin, S ^d   Poitevin, Y ^e   Ricapito, I ^f   Sardain, P ^e  

^a CEA SACLAY   (France)

^b POLITECNICO DI TORINO   (Italy)

^c JOINT RESEARCH CENTRE   (Italy)

^d IRFM   (France)

^e EFDA CLOSE SUPPORT UNIT   (Germany)

^f RSI Sistemi   (Italy)

Author keywords

Fusion blanket; Lithium lead; Permeation; Tritium

Indexed keywords

COOLING; FINITE ELEMENT METHOD; HELIUM;

HELIUM PURIFICATION; TEMPERATURE GRADIENTS; TRITIUM CONTROL MODELING;

TRITIUM;

EID: 31844442647     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2005.07.018     Document Type: Conference Paper

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