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URN: urn:nbn:de:swb:90-238111

Divertor Development for a Future Fusion Power Plant

Norajitra, Prachai

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.

Zugehörige Institution(en) am KIT Institut für Angewandte Materialien - Werkstoffprozesstechnik (IAM-WPT)
Publikationstyp Hochschulschrift
Jahr 2011
Sprache Englisch
Identifikator KITopen-ID: 1000023811
Verlag Karlsruhe
Abschlussart Dissertation
Fakultät Fakultät für Maschinenbau (MACH)
Institut Institut für Angewandte Materialien - Werkstoffprozesstechnik (IAM-WPT)
Prüfungsdaten 19.07.2011
Referent/Betreuer Prof. O. Kraft
Schlagworte Divertor, helium-cooled, jet impingement, high-heat-flux tests, tungsten manufacturing and braze joining
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