The ITER tritium systems

Fusion Engineering and Design

Volumn 82, Issue 5-14, 2007, Pages 472-487

  Glugla, M ^a,b   Antipenkov, A ^a   Beloglazov, S ^a   Caldwell Nichols, C ^a   Cristescu, I R ^a   Cristescu, I ^a   Day, C ^a   Doerr, L ^a   Girard, J P ^b   Tada, E ^b  

^a KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

^b ITER ORGANIZATION   (France)

Author keywords

Confinement; Detritiation; Fuel cycle design; ITER; Tritium Plant; Vacuum pumping

Indexed keywords

DECONTAMINATION; DEUTERIUM; EFFLUENTS; FLOW RATE; FUSION REACTIONS; TOKAMAK DEVICES;

DETRITIATION SYSTEMS; EQUIMOLAR DEUTERIUM TRITIUM MIXTURES; FUEL CYCLE DESIGN; NEUTRAL BEAM HEATING; VACUUM PUMPING;

TRITIUM;

EID: 34948890034     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2007.02.025     Document Type: Article

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