KIT | KIT-Bibliothek | Impressum | Datenschutz

Divertor Development for a Future Fusion Power Plant

Norajitra, Prachai

Abstract:

The thesis begins by describing the fusion process and operation of a fusion reactor, the approach in the conceptual development of a helium-cooled divertor, and leads to the KIT helium-cooled modular divertor design. Then the methods of verification and validation of the design by tests are described, results presented and discussed. The developed divertor concept has demonstrated its principal functionality and hence the used design process and tools can be conceived as verified and validated.


Volltext §
DOI: 10.5445/IR/1000023811
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Angewandte Materialien - Werkstoffprozesstechnik (IAM-WPT)
Publikationstyp Hochschulschrift
Publikationsjahr 2011
Sprache Englisch
Identifikator urn:nbn:de:swb:90-238111
KITopen-ID: 1000023811
Verlag Karlsruher Institut für Technologie (KIT)
Art der Arbeit Dissertation
Fakultät Fakultät für Maschinenbau (MACH)
Institut Institut für Angewandte Materialien - Werkstoffprozesstechnik (IAM-WPT)
Prüfungsdaten 19.07.2011
Schlagwörter Divertor, helium-cooled, jet impingement, high-heat-flux tests, tungsten manufacturing and braze joining
Relationen in KITopen
Referent/Betreuer Kraft, O.
KIT – Die Forschungsuniversität in der Helmholtz-Gemeinschaft
KITopen Landing Page