Thermal transients due to plasma sweeping on the monoblock divertor plate for iter

Journal Article · Tue Dec 01 04:00:00 EST 1992 · Fusion Technology; (United States)

OSTI ID:6987500

Renda, V; Papa, L; Soria, A ^[1]

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1. Commission of the European Communities, Ispra (Italy). Joint Research Centre

In this paper in the framework of the feasibility studies of the International Tokamak Experimental Reactor (ITER), the thermal behavior of the monoblock divertor plate has been investigated at the Joint Research Centre of the Commission of the European Communities. The design consists of cooling tubes embedded in a protective armor of graphite, a material that has given good results in plasma physics experiments. Previous parametric studies, based on a thermal flux peak of 15 MW/m[sup 2] and different materials, led to the choice of a Mo-Re alloy for the tubes and a high-conductivity carbon-fiber composite called SEP for the graphite armor. To comply with a design temperature of 1273 K, an allowable protective layer only 5 mm thick was indicated; however, because of the high erosion rate due to sputtering, the lifetime of such a plate would be unacceptable from an engineering standpoint. To overcome this difficulty, it has been proposed that the separatrix be swept to lower the flux peak during the transient. The nominal working condition then becomes a sweeping of the separatrix moving around the null point with a radius of 40 mm and frequency of 0.3 Hz: this generates a thermal load varying in time on the divertor plates. The results lead to the conclusion that plasma sweeping can reduce the surface temperature peak of the divertor, allowing a 16-mm-thick protective layer of the armor.

• OSTI ID: 6987500
• Journal Information: Fusion Technology; (United States), Journal Name: Fusion Technology; (United States) Vol. 22:4; ISSN 0748-1896; ISSN FUSTE8
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700410 -- Specific Fusion Devices & Experiments-- (1992-)
700420* -- Fusion Technology-- Plasma-Facing Components-- (1992-)
ALLOYS
CARBON
CLOSED PLASMA DEVICES
COMPOSITE MATERIALS
COOLING SYSTEMS
DESIGN
DIVERTORS
ELEMENTAL MINERALS
ELEMENTS
EROSION
FEASIBILITY STUDIES
FIBERS
GRAPHITE
HEAT FLUX
ITER TOKAMAK
LIFETIME
MATERIALS
MINERALS
MOLYBDENUM ALLOYS
NONMETALS
PLATES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
SERVICE LIFE
SPUTTERING
TEMPERATURE RANGE
TEMPERATURE RANGE 0400-1000 K
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
TRANSIENTS
TUBES