Published May 1976
| Version v1
Report
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Energy system for the generation of divertor magnetic fields in the PDX fusion research device
Description
One of the major problems encountered in the development of Tokamak type fusion reactors is the presence of impurities in the plasma. The PDX device is designed to study the operation of poloidal magnetic field divertors and consequent magnetic limiters for controlling and reducing the amount of impurities. A system of coils placed at specific locations produces a required field configuration for the poloidal divertor. This paper describes the system of energy supplies required and the interrelations of field coil currents during plasma current initiation, growth and steady state
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS.
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Additional details
Publishing Information
- Imprint Pagination
- 18 p.
- Report number
- MATT--1238
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7271847
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- DIVERTORS; ELECTRIC CURRENTS; IMPURITIES; LIMITERS; MAGNET COILS; POWER SUPPLIES; TOKAMAK DEVICES
- Descriptors DEC
- CLOSED PLASMA DEVICES; CURRENTS; ELECTRIC COILS; ELECTRICAL EQUIPMENT; ELECTRONIC EQUIPMENT; THERMONUCLEAR DEVICES
Optional Information
- Notes
- Available from NTIS. $3.50.