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Abstract An upgrade to the lower divertor is currently being planned for EAST superconducting tokamak, aiming at reaching over 400 s long-pulse H-mode operations with a full metal wall and a… Click to show full abstract
Abstract An upgrade to the lower divertor is currently being planned for EAST superconducting tokamak, aiming at reaching over 400 s long-pulse H-mode operations with a full metal wall and a divertor heat load of ˜10 MW/m2. A new divertor concept for EAST, “Tightly Baffled Divertor”, suited to water- cooled W/Cu plasma face components (PFC) with minimized divertor volume, has been proposed to achieve Te,target
Keywords:
poloidal field;
vessel poloidal;
divertor;
progress vessel;
field coils;
design
Journal Title: Fusion Engineering and Design
Year Published: 2019
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Journal Title: Fusion Engineering and Design
Year Published: 2019
Link to full text (if available)
Share on Social Media: Sign Up to like & get
recommendations!