Charge-exchange wall physical erosion rates for a proposed INTOR/FED limiter
We have analyzed power deposition and physical erosion rates on the first wall and limiter due to charge-exchange neutrals in a proposed pump limiter design for the INTOR/FED tokamak. Plasma conditions were modeled using the one-dimensional plasma transport code baldur. Neutral transport was modeled using a two-dimensional, multispecies Monte Carlo algorithm. No chemical erosion or wall redeposition processes were included. Two possible plasma discharges with different edge densities and temperatures were modeled, a regime with T/sub e/ approx.300 eV and napprox.5 x 10/sup 12/ cm/sup -3/, and a hotter, less dense edge regime produced with pellet fueling. We found that the erosion of the stainless steel vacuum vessel wall was highly localized in each case to the two points just beyond the limiter tips, and to the point directly across from the neutralizer plate, with peak erosion rates approx.2 cm/yr, assuming a 40% duty cycle. The erosion of a carbon limiter, neglecting redeposition and chemical erosion, varied in the two cases from 1.6--4 cm/yr, for the same duty cycle. The hotter, less dense discharge produced less sputtering. However achieving truly tolerable physical sputtering rates may require a very low edge temperature, plasma.
- Research Organization:
- Plasma Physics Laboratory, Princeton University, Princeton, New Jersey
- DOE Contract Number:
- AC02-76CH03073
- OSTI ID:
- 5723650
- Journal Information:
- J. Vac. Sci. Technol., A; (United States), Journal Name: J. Vac. Sci. Technol., A; (United States) Vol. 1:2; ISSN JVTAD
- Country of Publication:
- United States
- Language:
- English
Similar Records
Performance of the INTOR poloidal divertor
Performance of the INTOR poloidal divertor
Related Subjects
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
CARBON
CHARGE EXCHANGE
CHARGED-PARTICLE TRANSPORT
CHROMIUM ALLOYS
COMPUTERIZED SIMULATION
CORROSION RESISTANT ALLOYS
DEPOSITION
DESIGN
ELECTRIC DISCHARGES
ELECTRON TEMPERATURE
ELEMENTS
EROSION
FEASIBILITY STUDIES
FIRST WALL
FUEL PELLETS
HOT PLASMA
IMPURITIES
INTOR TOKAMAK
IRON ALLOYS
IRON BASE ALLOYS
LIMITERS
MATHEMATICAL MODELS
MONTE CARLO METHOD
NONMETALS
PELLETS
PLASMA
PLASMA DENSITY
PLASMA SIMULATION
POWER INPUT
RADIATION TRANSPORT
SIMULATION
SPUTTERING
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
VACUUM SYSTEMS