Particle reflection and neutral transport in the edge of ITER
A 2-D Monte-Carlo simulation of the neutral atom densities in the divertor throat, private flux region, and pump duct of ITER were made using the DEGAS code. Plasma conditions were modelled using the B2 plasma transport code. Wall reflection coefficients including the effect of realistic surface roughness were determined by using the Fractal TRIM code. Results were obtained for both helium and deuterium. Pumping ratios and the effects of geometry are discussed. It is found that the detailed geometry and wall model have a significant effect on the helium pumping ratio and neutral atom density profiles. 12 figs.
- Research Organization:
- Illinois Univ., Urbana, IL (USA)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- FG02-89ER52159
- OSTI ID:
- 6980677
- Report Number(s):
- DOE/ER/52159-1; ON: DE90008656
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700103* -- Fusion Energy-- Plasma Research-- Kinetics
CLOSED PLASMA DEVICES
DIVERTORS
DOCUMENT TYPES
ELEMENTS
FIRST WALL
FLUIDS
GASES
HELIUM
ITER TOKAMAK
NEUTRAL-PARTICLE TRANSPORT
NONMETALS
PLASMA SIMULATION
PROGRESS REPORT
RADIATION TRANSPORT
RARE GASES
ROUGHNESS
SIMULATION
SURFACE PROPERTIES
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
TOKAMAK DEVICES
700103* -- Fusion Energy-- Plasma Research-- Kinetics
CLOSED PLASMA DEVICES
DIVERTORS
DOCUMENT TYPES
ELEMENTS
FIRST WALL
FLUIDS
GASES
HELIUM
ITER TOKAMAK
NEUTRAL-PARTICLE TRANSPORT
NONMETALS
PLASMA SIMULATION
PROGRESS REPORT
RADIATION TRANSPORT
RARE GASES
ROUGHNESS
SIMULATION
SURFACE PROPERTIES
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
TOKAMAK DEVICES