Impurity control and vacuum pumping system design and analysis for next-generation tokamaks
Conference
·
· Fusion Technol.; (United States)
OSTI ID:5876623
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-
- Conference Information:
- Journal Name: Fusion Technol.; (United States) Journal Volume: 8:1
- Country of Publication:
- United States
- Language:
- English
Similar Records
Impurity control and vacuum pumping system design and analysis for next-generation tokamaks
TFCX pumped limiter and vacuum pumping system design and analysis
Tokamak Fusion Core Experiment (TFCX) special-purpose remote maintenance systems
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:5835269
TFCX pumped limiter and vacuum pumping system design and analysis
Technical Report
·
Sun Mar 31 23:00:00 EST 1985
·
OSTI ID:5882107
Tokamak Fusion Core Experiment (TFCX) special-purpose remote maintenance systems
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:5981757
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
COATINGS
CONTROL
CONTROL SYSTEMS
DESIGN
ELEMENTS
EQUIPMENT
EROSION
EXHAUST GASES
FLUIDS
GASEOUS WASTES
GASES
HELIUM
IMPURITIES
LABORATORY EQUIPMENT
LIMITERS
NONMETALS
PERFORMANCE
PROTECTIVE COATINGS
PUMPED LIMITERS
PUMPS
RARE GASES
SERVICE LIFE
TEMPERATURE EFFECTS
TFCX REACTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
VACUUM PUMPS
VACUUM SYSTEMS
WASTES
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
COATINGS
CONTROL
CONTROL SYSTEMS
DESIGN
ELEMENTS
EQUIPMENT
EROSION
EXHAUST GASES
FLUIDS
GASEOUS WASTES
GASES
HELIUM
IMPURITIES
LABORATORY EQUIPMENT
LIMITERS
NONMETALS
PERFORMANCE
PROTECTIVE COATINGS
PUMPED LIMITERS
PUMPS
RARE GASES
SERVICE LIFE
TEMPERATURE EFFECTS
TFCX REACTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
VACUUM PUMPS
VACUUM SYSTEMS
WASTES