Assessment of the He-cooled Test Divertor Module for ITER

Fusion Engineering and Design

Volumn 83, Issue 7-9, 2008, Pages 1131-1136

  Widak, V ^a   Norajitra, P ^a   Boccaccini, L V ^a   Janeschitz, G ^a  

^a KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

Author keywords

Helium cooled divertor; HEMJ concept; Test divertor module (TDM)

Indexed keywords

ELECTRIC POWER PLANTS; EXPERIMENTAL REACTORS; INERT GASES; POWER PLANTS; TIME DIVISION MULTIPLEXING;

DIVERTOR CONCEPTS; FORSCHUNGSZENTRUM KARLSRUHE; HELIUM COOLING; HEMJ CONCEPT; PIPING LAYOUTS; POWER PLANT CONCEPTUAL STUDIES; REMOTE HANDLINGS;

HELIUM;

EID: 56949095317     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2008.06.017     Document Type: Article

References (6)

1. Norajitra P. He-cooled divertor development for DEMO. Fusion Eng. Design 82 (2007) 2740-2744
2. R. Kruessmann, P. Norajitra, Conceptual design of a He-cooled divertor with integrated flow and heat transfer promoters, FZKA 6975, April 2004
3. Design description document WBS1.7 Divertor, July 2001.
4. Verband der Technischen Überwachungs-Vereine e.V., AD 2000, Regelwerk, Carl Heymanns Verlag, Essen, 2003.
5. Design description document DDD23, July 2004.
6. Neuberger H. Helium loop for the HCPB test blanket module. Fusion Eng. Design 82 (2007) 2288-2293