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Erosion

Author: Brooks, J.N.; Argonne National Lab., IL (USA). Fusion Power Program; Argonne National Lab.; United States. Department of Energy. Office of Scientific and Technical Information.
Publisher: Argonne, Ill. : Argonne National Lab ; Oak Ridge, Tenn. : distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1989.
Edition/Format:   eBook : Document : National government publication : English
Database:WorldCat
Summary:
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  Read more...
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Material Type: Document, Government publication, National government publication, Internet resource
Document Type: Internet Resource, Computer File
All Authors / Contributors: Brooks, J.N.; Argonne National Lab., IL (USA). Fusion Power Program; Argonne National Lab.; United States. Department of Energy. Office of Scientific and Technical Information.
OCLC Number: 727285542
Notes: Published through the Information Bridge: DOE Scientific and Technical Information.
07/01/1989.
"anl/fpp/tm-242"
"DE89016704"
Brooks, J.N.
Argonne National Lab., IL (USA). Fusion Power Program.
Description: Pages: 30 : digital, PDF file.
Responsibility: redeposition analysis of the ITER (International Tokamak Engineering Reactor) divertor

Abstract:

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.

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