Performance of the INTOR poloidal divertor
Journal Article
·
· J. Vac. Sci. Technol.; (United States)
The next generation of large tokamak experiments is expected to have large particle and heat outfluxes (approx.10/sup 23/ particles/s and 80 MW). These outfluxes must be controlled to provide adequate pumping of the helium ''ash'' and to minimize the sputtering erosion of the vacuum vessel walls, limiters, and neutralizer plates. A poloidal divertor design to solve these problems for INTOR has been done using a two-dimensional code which models the plasma as a fluid and solves equations for the flow of particles, momentum and energy, and calculates the neutral gas transport with Monte-Carlo techniques. These calculations show that there is a regime of operation where the density in the divertor is high and the temperature is low, thus easing the heat load and erosion problems. The neutral pressure at the plate is high, resulting in high gas throughputs with modest pumping speeds.
- Research Organization:
- Princeton University, Plasma Physics Laboratory, Princeton, New Jersey 08544
- OSTI ID:
- 5413969
- Journal Information:
- J. Vac. Sci. Technol.; (United States), Journal Name: J. Vac. Sci. Technol.; (United States) Vol. 20:4; ISSN JVSTA
- Country of Publication:
- United States
- Language:
- English
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· Phys. Rev. Lett.; (United States)
·
OSTI ID:5413936
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700101 -- Fusion Energy-- Plasma Research-- Confinement
Heating
& Production
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
CLOSED PLASMA DEVICES
COMPUTER CODES
COMPUTER-AIDED DESIGN
COMPUTERIZED SIMULATION
DESIGN
DIVERTORS
ELEMENTS
ENERGY TRANSPORT
FLUID FLOW
FLUIDS
GASES
HEAT FLUX
HELIUM
IMPURITIES
MOMENTUM TRANSFER
MONTE CARLO METHOD
NONMETALS
PLASMA SIMULATION
POLOIDAL DIVERTORS
PUMPING
RARE GASES
SIMULATION
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
TWO-DIMENSIONAL CALCULATIONS
VACUUM SYSTEMS
WALLS
700101 -- Fusion Energy-- Plasma Research-- Confinement
Heating
& Production
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
CLOSED PLASMA DEVICES
COMPUTER CODES
COMPUTER-AIDED DESIGN
COMPUTERIZED SIMULATION
DESIGN
DIVERTORS
ELEMENTS
ENERGY TRANSPORT
FLUID FLOW
FLUIDS
GASES
HEAT FLUX
HELIUM
IMPURITIES
MOMENTUM TRANSFER
MONTE CARLO METHOD
NONMETALS
PLASMA SIMULATION
POLOIDAL DIVERTORS
PUMPING
RARE GASES
SIMULATION
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
TWO-DIMENSIONAL CALCULATIONS
VACUUM SYSTEMS
WALLS