Performance of the INTOR poloidal divertor
The next generation of large tokamak experiments is expected to have large particle and heat outfluxes (approx. 10/sup 23/ particles/sec 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 Univ., NJ (USA). Plasma Physics Lab.
- DOE Contract Number:
- AC02-76CH03073
- OSTI ID:
- 6130148
- Report Number(s):
- PPPL-1835; ON: DE82001351
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
DIVERTORS
ELEMENTS
EROSION
FIRST WALL
FLUIDS
GASES
HELIUM
IMPURITIES
INTOR TOKAMAK
LIMITERS
NONMETALS
PERFORMANCE
POLOIDAL DIVERTORS
RARE GASES
REMOVAL
SPUTTERING
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TWO-DIMENSIONAL CALCULATIONS
VACUUM SYSTEMS