ITER divertor sputtering erosion -- recent analysis for carbon, beryllium, tungsten, and niobium surfaces

Technical Report · Mon Jul 01 04:00:00 EDT 1991

DOI:https://doi.org/10.2172/5439807· OSTI ID:5439807

Brooks, J N

ITER divertor plate sputtering erosion has been analyzed using current design information and updated impurity transport models. The REDEP erosion/redeposition code was used to compute erosion for a very low plasma divertor temperature (T{sub e{sub 0}} {approx} 12 eV) physics phase reference'' case, and for other plasma conditions. A high surface temperature case (T{sub s{sub 0}} = 1800{degree}C) is analyzed for a carbon surface. Niobium is analyzed using WBC near-surface transport code results for the redeposited charge state. The REDEP results show high net erosion rates ({approx gt} 20 cm/burn{sm bullet}yr) for beryllium and carbon, even at low plasma temperatures. Net erosion rates are low to moderate for niobium ({approximately}0-3 cm/burn{sm bullet}yr), depending on plasma conditions, and low for tungsten ({approximately}0-0.2 cm/burn{sm bullet}yr). 9 refs., 2 figs.

• 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: 5439807
• Report Number(s): ANL/FPP/TM-255; ON: DE91017235
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
360604 -- Materials-- Corrosion
Erosion
& Degradation
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALINE EARTH METALS
BERYLLIUM
CARBON
CLOSED PLASMA DEVICES
DESIGN
DIVERTORS
ELECTRON TEMPERATURE
ELEMENTS
EROSION
IMPURITIES
ITER TOKAMAK
MATERIALS
METALS
NIOBIUM
NONMETALS
PLASMA IMPURITIES
SPUTTERING
SURFACES
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR MATERIALS
TOKAMAK DEVICES
TRANSITION ELEMENTS
TUNGSTEN