Impurity control and vacuum pumping system design and analysis for next-generation tokamaks
Impurity control system design and performance studies were performed in support of the Tokamak Fusion Core Experiment (TFCX) preconceptual design. Efforts concentrated on the pumped limiter and vacuum pumping system design configuration, thermal/mechanical and erosion lifetime performance of the limiter protective surface, and helium ash removal performance. Analysis results indicate that the limiter/vacuum pumping system design provides marginally adequate helium ash removal. Difficulties in providing adequate helium ash removal for more compact or higher fusionpower-density devices are addressed. Erosion, primarily by disruption-induced vaporization and/or melting, limits the protective surface lifetime to about one calendar year or only about 60 full-power hours of operation. In addition to evaluating impurity control system performance for nominal TFCX conditions, these studies attempt to focus on the key plasma physics and engineering design issues that should be addressed in future research and development programs.
- Research Organization:
- Fusion Engineering Design Center/Oak Ridge National Laboratory, Oak Ridge, TN
- OSTI ID:
- 5876623
- Report Number(s):
- CONF-850310-
- Journal Information:
- Fusion Technol.; (United States), Vol. 8:1; Conference: 6. topical meeting on the technology of fusion energy, San Francisco, CA, USA, 3 Mar 1985
- Country of Publication:
- United States
- Language:
- English
Similar Records
TFCX pumped limiter and vacuum pumping system design and analysis
Engineering design of a liquid metal cooled self-pumped limiter for a tokamak reactor
Related Subjects
IMPURITIES
CONTROL
PUMPED LIMITERS
DESIGN
PERFORMANCE
VACUUM PUMPS
TFCX REACTORS
CONTROL SYSTEMS
EROSION
EXHAUST GASES
HELIUM
PROTECTIVE COATINGS
SERVICE LIFE
TEMPERATURE EFFECTS
VACUUM SYSTEMS
COATINGS
ELEMENTS
EQUIPMENT
FLUIDS
GASEOUS WASTES
GASES
LABORATORY EQUIPMENT
LIMITERS
NONMETALS
PUMPS
RARE GASES
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
WASTES
700201* - Fusion Power Plant Technology- Blanket Engineering
700209 - Fusion Power Plant Technology- Component Development & Materials Testing