The performance of the poloidal divertor experiment neutral beam wall armor

Journal Article · Thu May 01 04:00:00 EDT 1986 · Fusion Technol.; (United States)

OSTI ID:5653994

Kugel, H W; Eubank, H P; Kozub, T A; Williams, M D; Ulrickson, M

During 2 yr of experimental operations, the Poloidal Divertor Experiment (PDX) inner wall neutral beam graphite armor provided protection for perpendicular heating injections into normal and disruptive plasmas as well as injection in the absence of plasma for special experiments, calibrations, and tests involving the optimization and development of the PDX neutral beam injection system. About 80 to 100 heating injections occurred per operating day, at a 360-s duty cycle, into plasmas of various densities, and typically approx. =5 to 50% of the injected neutral beam power was transmitted to the armor. More than 10/sup 3/ neutral beam pulses of 100- to 300-ms duration were injected in the absence of plasma at peak power densities of 1.5 to 3 kW/cm/sup 2/, yielding peak surface temperatures of 950 to 1550/sup 0/C. There was no significant impurity production attributable to beam heating of the armor, and no observed beam-induced, macroscopic surface damage. Many of the design constraints and performance issues encountered in this work are relevant to the design of larger fusion devices.

• Research Organization: Plasma Physics Lab., Princeton Univ., Princeton, NJ 08544
• OSTI ID: 5653994
• Journal Information: Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 9:3; ISSN FUSTE
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
BEAM INJECTION
CALIBRATION
CARBON
CLOSED PLASMA DEVICES
DAMAGE
DESIGN
ELEMENTAL MINERALS
ELEMENTS
GRAPHITE
IMPURITIES
MINERALS
NEUTRAL ATOM BEAM INJECTION
NONMETALS
OPTIMIZATION
PDX DEVICES
PERFORMANCE TESTING
PLASMA DENSITY
POWER DENSITY
PULSES
RESEARCH PROGRAMS
SHIELDS
SURFACE PROPERTIES
TESTING
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
VERY HIGH TEMPERATURE