The design of the poloidal divertor experiment tokamak wall armor and inner limiter system

Journal Article · Fri Oct 01 04:00:00 EDT 1982 · Nucl. Technol./Fusion; (United States)

OSTI ID:5591467

Kugel, H W; Ulrickson, M

The inner wall protective plates for the Poloidal Divertor Experiment Tokamak are designed to absorb 8 MW of neutral deuterium beam power at maximum power densities of 3 kW/cm/sup 2/ for pulse lengths of 0.5 s. Preliminary studies indicate that the design could survive several pulses of l-s duration. The design consists of a tile and mounting plate structure. The mounting plates are water cooled to allow short duty cycles and beam calorimetry. The temperature and flow of the coolant are measured to obtain the injected power. A thermocouple array on the tiles provides beam position and power density profiles. Several material combinations for the tiles were subjected to thermal tests using both electron and neutral beams, and titanium-carbidecoated graphite was selected as the tile material. The heat transfer coefficient of the tile backing plate structure was measured to determine the maximum pulse rate allowable. The design of the armor system allows the structure to be used as a neutral beam power diagnostic and as an inner plasma limiter. The electrical and cooling systems external to the vacuum vessel are discussed.

• Research Organization: Princeton University, Princeton Plasma Physics Laboratory, P.O. Box 451, Princeton, New Jersey 08544
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 5591467
• Journal Information: Nucl. Technol./Fusion; (United States), Journal Name: Nucl. Technol./Fusion; (United States) Vol. 2:4; ISSN NTFUD
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
BEAM INJECTION
CARBON
CONFINEMENT
COOLANTS
DESIGN
DIVERTORS
ELEMENTAL MINERALS
ELEMENTS
ENERGY TRANSFER
FLOW RATE
GRAPHITE
HEAT TRANSFER
MEASURING INSTRUMENTS
MINERALS
NEUTRAL ATOM BEAM INJECTION
NEUTRAL BEAM SOURCES
NONMETALS
PLASMA CONFINEMENT
POLOIDAL DIVERTORS
POWER DENSITY
TEMPERATURE MEASUREMENT
THERMOCOUPLES
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
WALL LOADING