Development and operation of PDX neutral beam computer system

Conference · Thu Jan 01 00:00:00 EST 1981 · Proc. Symp. Eng. Probl. Fusion Res.; (United States)

OSTI ID:6361598

Kozub, T; Rossmassler, J E; Eubank, H P; Kugel, H W; Schilling, G; von Halle, A; Williams, M D

The Poloidal Divertor Experiment (PDX) is a tokamak experiment designed to study impurity control through the use of magnetic divertors utilizing four neutral beams for heating. Each beamline is equipped with a 30 cm diameter ORNL source providing either 1.5 MW H/degree/or 2.0 MW D/degree/. The four neutral beam injectors have succeeded in reliably delivering 7 mega-watts of neutral beam power into PDX. The PDX neutral beam computer system supports the operation of the beamlines including ion sources and related diagnostics. A dedicated DEC PDP 11/34 computer is interfaced to the neutral beam components through a five crate CAMAC parallel/serial highway system.

• Research Organization: Princeton Univ, NJ, USA
• OSTI ID: 6361598
• Report Number(s): CONF-811040-; TRN: 83-008047
• Journal Information: Proc. Symp. Eng. Probl. Fusion Res.; (United States), Conference: 9. symposium on engineering problems of fusion research, Chicago, IL, USA, 26 Oct 1981
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
NEUTRAL BEAM SOURCES
COMPUTERIZED CONTROL SYSTEMS
PDX DEVICES
CAMAC SYSTEM
DATA ACQUISITION
OPERATION
PLASMA HEATING
CONTROL SYSTEMS
DIVERTORS
HEATING
700205* - Fusion Power Plant Technology- Fuel
Heating
& Injection Systems