Design of the PDX Tokamak wall armor and inner limiter system

Technical Report · Sat Aug 01 04:00:00 EDT 1981

DOI:https://doi.org/10.2172/6278317· OSTI ID:6278317

Kugel, H W; Ulrickson, M

The inner wall protective plates for the PDX 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 sec. Preliminary studies indicate that the design could survive several pulses of 1 sec 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 is 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 carbide coated 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 Univ., NJ (USA). Plasma Physics Lab.
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 6278317
• Report Number(s): PPPL-1785; ON: DE81030885
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
CARBIDES
CARBON
CARBON COMPOUNDS
COOLING SYSTEMS
DIVERTORS
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
GRAPHITE
LIMITERS
NONMETALS
PDX DEVICES
SAFETY
SHIELDING
TITANIUM CARBIDES
TITANIUM COMPOUNDS
TRANSITION ELEMENT COMPOUNDS