ARIES-III divertor engineering design

Conference · Tue Dec 31 23:00:00 EST 1991

OSTI ID:5793620

Wong, C P.C.; Schultz, K R ^[1]; Cheng, E T ^[2]; Grotz, S; Hasan, M A; Najmabadi, F; Sharafat, S ^[3]; Brooks, J N; Ehst, D A; Sze, D K ^[4]; Herring, J S ^[5]

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1. General Atomics, San Diego, CA (United States)
2. TSI Research, Solana Beach, CA (United States)
3. California Univ., Los Angeles, CA (United States). Dept. of Mechanical, Aerospace and Nuclear Engineering
4. Argonne National Lab., IL (United States)
5. EG and G

This paper reports the engineering design of the ARIES-III double- null divertor. The divertor coolant tubes are made from W-3Re alloy and cooled by subcooled flow boiling of organic coolant. A coating of 4 mm thick tungsten is plasma sprayed onto the divertor surface. This W layer can withstand the thermal deposition of a few disruptions. At a maximum surface heat flux of 5.4 MW/m{sup 2}, a conventional divertor design can be used. The divertor surface is contoured to have a constant heat flux of 5.4 MW/m{sup 2}. The net erosion of the W-surface was found to be negligible at about 0.1 mm/year. After 3 years of operation, the W-3Re alloy ARIES-III divertor can be disposed of as Class A waste. In order to control the prompt dose release at site boundary to less than 200 Rem, isotopic tailoring of the W-alloy will be needed.

• Research Organization: General Atomics, San Diego, CA (United States)
• Sponsoring Organization: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC03-89ER52153
• OSTI ID: 5793620
• Report Number(s): GA-A-20734; CONF-910968--66; ON: DE92006913
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700420* -- Fusion Technology-- Plasma-Facing Components-- (1992-)
CLOSED PLASMA DEVICES
DESIGN
DIVERTORS
ELEMENTS
ENERGY TRANSFER
EROSION
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICS
METALS
SHIELDING
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
TRANSITION ELEMENTS
TUNGSTEN