Modeling of erosion and redeposition processes
Conference
·
OSTI ID:6564540
The purpose of erosion/redeposition (E/R) modeling is to predict the effects of sputtering on: (1) erosion rates and lifetimes of tokamak divertors, limiters, and th first wall, (2) tritium co-deposition, and (3) plasma contamination. Because of the specialized and complex phenomena associated with surface derived impurities, in particular surface interactions, sheath transport, and multiple charge state effects, it has proven useful to develop models and computer codes specifically for E/R calculations. These are used in conjunction with codes and analysis of th background hydrogen plasma. The E/R codes fall primarily into two categories: (1) trace impurity content codes for treatment of near-surface and scrape-off layer (SOL) transport, and (2) non-trace codes, e.g., for self-consistent, oblique magnetic field sheath calculations within-sheath ionization of sputtered impurities. The intent of this paper is to review current research activities in E/R modeling with emphasis on the codes mentioned above. Recent applications are describe including analysis for the ITER divertor. Results of several recent code verification activities via comparison with experimental data are discussed. Data needs an sensitivity to ionization rate uncertainties are also discussed. A brief description of work in the key area of surface roughness modeling is included.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6564540
- Report Number(s):
- ANL/EP/CP-78386; CONF-921053--3; ON: DE93008649
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700420* -- Fusion Technology-- Plasma-Facing Components-- (1992-)
700480 -- Fusion Technology-- Component Development
CLOSED PLASMA DEVICES
DIVERTORS
EROSION
FIRST WALL
IMPURITIES
LIMITERS
MATHEMATICAL MODELS
Ma
Materials Studies-- (1992-)
PLASMA IMPURITIES
PLASMA SHEATH
SPUTTERING
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
TOKAMAK DEVICES
700420* -- Fusion Technology-- Plasma-Facing Components-- (1992-)
700480 -- Fusion Technology-- Component Development
CLOSED PLASMA DEVICES
DIVERTORS
EROSION
FIRST WALL
IMPURITIES
LIMITERS
MATHEMATICAL MODELS
Ma
Materials Studies-- (1992-)
PLASMA IMPURITIES
PLASMA SHEATH
SPUTTERING
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
TOKAMAK DEVICES