Published November 1, 1999 | Version v1
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Features and Initial Results of the DIII-D Advanced Tokamak Radiative Divertor

Description

The Radiative Divertor Program of DIII-D is in its final phase with the installation of the cryopump and baffle structure (Phase 1B Divertor) in the upper inner radius of the DIII-D vacuum vessel at the end of this calendar year. This divertor, in conjunction with the Advanced Divertor and the Phase 1A Divertor, located in the lower and upper outer radius of the DIII-D vacuum vessel respectively, provides pumping for density control of the plasma while minimizing the effects on the core confinement. Each divertor consists of a cryobelium cooling ring and a shielded protective structure. The cryo/helium-cooled pumps of all three diverters exhaust helium from the plasma. The protective shielded structure or baffle structure, in the case of the diverters located at the top of the vacuum vessel, provides baffling of neutral charged particles and minimize the flow of impurities back into the core of the plasma. The baffles, which consist of water-cooled panels that allow for the attachment of tiles of various sizes and shapes, house gas puff systems. The intent of the puffing systems is to inject gas in and around the divertor to minimize the heat flux on specific areas on the divertor and its components. The reduction of the heat flux on the divertor minimizes the impurities that are generated from excess heat on divertor components, specifically tiles. Experiments involving the gas puff systems and the divertor structures have shown the heat flux can be spread over a large area of the divertor, reducing the peak heat flux in specific areas. The three diverters also incorporate a variety of diagnostic tools such as halo current monitors, magnetic probes and thermocouples to monitor certain plasma characteristics as well as determine the effectiveness of the cryopumps and baffle configurations. The diverters were designed to optimize pumping performance and to withstand the electromagnetic loads from both halo currents and toroidal induced currents. Incorporated also into the designs of the structures is the capability to withstand the thermal gradient across the structures and the DIII-D vacuum vessel during operations and bakeout in which temperatures reach as high as 350 C. The performance of the diagnostics and divertor systems with experimental results of the two existing systems are reported in this paper along with the baseline of the designs of the three divertor systems

Availability note (English)

Available from INIS in electronic form; Also available from OSTI as DE00766809; PURL: https://www.osti.gov/servlets/purl/766809-4oUwhQ/webviewable/

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Additional details

Publishing Information

Imprint Pagination
7 p.
Report number
GA-A--23284

Conference

Title
18. IEEE/NPSS Symposium on Fusion Engineering
Dates
25-29 Oct 1999
Place
Albuquerque, NM (United States)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
33002431
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BAFFLES; CRYOPUMPS; DIVERTORS; DOUBLET-3 DEVICE; HEAT FLUX; MAGNETIC PROBES; PERFORMANCE; PLASMA DENSITY; PROCESS CONTROL; TEMPERATURE GRADIENTS
Descriptors DEC
CLOSED PLASMA DEVICES; CONTROL; CONTROL EQUIPMENT; EQUIPMENT; FLOW REGULATORS; LABORATORY EQUIPMENT; PROBES; PUMPS; THERMONUCLEAR DEVICES; TOKAMAK DEVICES; VACUUM PUMPS

Optional Information

Contract/Grant/Project number
AC03-99ER54463; W-7405-ENG-48
Funding organization
US Department of Energy (United States)