Published January 1981
| Version v1
Report
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PDX experimental results
Description
The main objectives of the Poloidal Divertor Experiment (PDX) are to: (1) determine the effectiveness of poloidal divertors in controlling impurities in high temperature plasmas, (2) use the poloidal divertor to provide clean plasmas for confinement and high beta studies, and (3) investigate the effect of cross-section shaping on plasma confinement and MHD properties. In this paper, we report the results obtained during initial divertor operation of the PDX
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.Files
12606153.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 32 p.
- Report number
- PPPL--1740
Conference
- Title
- 8. international conference on plasma physics and controlled nuclear fusion research.
- Dates
- 1 - 10 Jul 1980.
- Place
- Brussels, Belgium.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12606153
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- IMPURITIES; MAGNET COILS; OPERATION; PDX DEVICES; PERFORMANCE; SHAPE
- Descriptors DEC
- CONFIGURATION; DIVERTORS; ELECTRIC COILS; ELECTRICAL EQUIPMENT
Optional Information
- Secondary number(s)
- CONF-800707--25.