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Divertor Development for a Future Fusion Power Plant
Prachai Norajitra
2014
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Nuclear fusion is considered as a future source of sustainable energy supply. Since the H-mode discovery in ASDEX experiment ""Divertor I"" in 1982, the divertor has been an integral part of all modern tokamaks and stellarators. The major goal of this thesis is to develop a feasible divertor design for a fusion power plant to be built after ITER. The thesis describes the approach in the conceptual development of a helium-cooled divertor and the methods of verification and validation of the design.
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Keywords
- Fusion power plant
- helium impingement cooling
- helium-cooled divertor
- high heat flux tests
- machining and joining tungsten
Links
DOI: 10.5445/KSP/1000024270Editions