Published January 1981 | Version v1
Report Open

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.

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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.