Progress in engineering design of Indian LLCB TBM set for testing in ITER

•The tritium breeding for LLCB TBM has been evaluated by neutronic analysis.•Details of thermal-hydraulic analyses performed for FW and internal components of LLCB TBM and shield block have been provided..•The optimum dimensions of CB zones and Pb–Li flow have been selected to have the maximum tempe...

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Veröffentlicht in:	Fusion engineering and design 2014-10, Vol.89 (7-8), p.1362-1369
Hauptverfasser:	Chaudhuri, Paritosh, Ranjithkumar, S., Sharma, Deepak, Danani, Chandan, Swami, H.L., Bhattacharya, R., Patel, Anita, Kumar, E. Rajendra, Vyas, K.N.
Format:	Artikel
Sprache:	eng
Schlagworte:	Blanketing Blocking Ceramics First wall Frames Helium ITER LLCB Modules Ports Shield block Shields TBM Thermal-hydraulics
Online-Zugang:	Volltext
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