Erosion/redeposition analysis of the ITER (International Tokamak Engineering Reactor) divertor

Technical Report · Sat Jul 01 00:00:00 EDT 1989

DOI:https://doi.org/10.2172/5807069· OSTI ID:5807069

Brooks, J N

Sputtering erosion of the proposed ITER divertor has been analyzed using the REDEP computer code. A carbon coated plate at medium and low plasma edge temperatures, as well as beryllium and tungsten plates, have been examined. Peak net erosion rates for C and Be are very high (/approximately/20--80 cm/burn/center dot/yr) though an order of magnitude less than the gross rates. Tritium buildup rates in codeposited carbon surface layers may also be high (/approximately/50--250 kg/burn/center dot/yr). Plasma contamination, however, from divertor sputtering is low (/approx lt/.5%). Operation with low Z divertor plates, at high duty factors, therefore appears unacceptable due to erosion, but may work for low duty factor (/approximately/2%) ''physics phase'' operation. Sweeping of the poloidal field lines at the divertor can reduce erosion, by typical factors of /approximately/2--8. A tungsten coated plate works well, from the erosion standpoint, for plasma plate temperatures of /approximately/40 eV or less. 18 refs., 11 figs., 3 tabs.

• Research Organization: Argonne National Lab., IL (USA). Fusion Power Program
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5807069
• Report Number(s): ANL/FPP/TM-242; ON: DE89016704
• Resource Relation: Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DIVERTORS
EROSION
IMPURITIES
ITER TOKAMAK
MATERIALS TESTING
SPUTTERING
THERMONUCLEAR REACTOR MATERIALS
TUNGSTEN
CLOSED PLASMA DEVICES
ELEMENTS
MATERIALS
METALS
TESTING
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
TRANSITION ELEMENTS
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