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Alcator C-Mod Design, Engineering, and Disruption Research
- Source :
- Fusion Science and Technology. 51:460-475
- Publication Year :
- 2007
- Publisher :
- Informa UK Limited, 2007.
-
Abstract
- We describe some of the engineering solutions required to produce a diverted tokamak capable of operation with a toroidal field of 8 T and plasma currents of up to 2 MA. Some design details of the toroidal field magnet, the ohmic heating magnet, the metal plasma-facing components, the rf heating and current drive systems, and the power and liquid nitrogen cooling systems are discussed. Vacuum, vessel bake, boronization, and wall-cleaning systems are also discussed. Finally, disruption research results from Alcator C-Mod are presented.
- Subjects :
- Nuclear and High Energy Physics
Tokamak
Materials science
020209 energy
Mechanical Engineering
Nuclear engineering
02 engineering and technology
Plasma
01 natural sciences
010305 fluids & plasmas
law.invention
Nuclear Energy and Engineering
Alcator C-Mod
Physics::Plasma Physics
law
Magnet
0103 physical sciences
Dielectric heating
0202 electrical engineering, electronic engineering, information engineering
General Materials Science
Vacuum chamber
Atomic physics
Current (fluid)
Joule heating
Civil and Structural Engineering
Subjects
Details
- ISSN :
- 19437641 and 15361055
- Volume :
- 51
- Database :
- OpenAIRE
- Journal :
- Fusion Science and Technology
- Accession number :
- edsair.doi...........dadb491422f1371273f836595628ad44