Neutral Transport and Helium Pumping of ITER (Annual Progress Report for period January 15, 1990 - January 14, 1991)

Technical Report · Wed Aug 01 04:00:00 EDT 1990

DOI:https://doi.org/10.2172/6242897· OSTI ID:6242897

Ruzic, David N. ^[1]

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1. Univ. of Illinois at Urbana-Champaign, IL (United States)

A 2-D Monte-Carlo simulation of the neutral atom densities in the divertor, divertor throat and pump duct of ITER was made using the DEGAS code. Plasma conditions in the scrape-off layer and region near the separatrix were modeled using the B2 plasma transport code. Wall reflection coefficients including the effect of realistic surface roughness were determined by using the fractal TRIM code. The DEGAS and B2 coupling was iterated until a consistent recycling was predicted. Results were obtained for a helium and a deuterium/tritium mixture on 7 different ITER divertor throat geometries for both the physics phase reference base case and a technology phase case. The geometry with a larger structure on the midplane-side of the throat opening closing the divertor throat and a divertor plate which maintains a steep slope well into the throat removed helium 1.5 times better than the reference geometry for the physics phase case and 2.2 times better for the technology phase case. At the same time the helium to hydrogen pumping ratio shows a factor of 2.34 {plus minus} .41 enhancement over the ratio of helium to hydrogen incident on the divertor plate in the physics phase and an improvement of 1.61 ± .31 in the technology phase. If the helium flux profile on the divertor plate is moved outward by 20 cm with respect to the D/T flux profile for this particular geometry, the enhancement increases to 4.36 {plus minus} .90 in the physics phase and 5.10 ± .92 in the technology phase.

• Research Organization: Univ. of Illinois at Urbana-Champaign, IL (United States)
• Sponsoring Organization: USDOE Office of Energy Research (ER)
• DOE Contract Number: FG02-89ER52159
• OSTI ID: 6242897
• Report Number(s): DOE/ER/52159--2; ON: DE91007912
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
BOUNDARY LAYERS
CHARGED PARTICLES
CLOSED PLASMA DEVICES
COMPUTERIZED SIMULATION
DIVERTORS
DOCUMENT TYPES
HELIUM ASH
HELIUM IONS
IONS
ITER TOKAMAK
LAYERS
MONTE CARLO METHOD
PLASMA SCRAPE-OFF LAYER
PROGRESS REPORT
PUMPING
SIMULATION
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
TRANSPORT THEORY