Neutronic calculations for the Tokamak fusion test reactor diagnostic penetrations

Journal Article · Thu Apr 01 04:00:00 EST 1982 · Nucl. Technol./Fusion; (United States)

OSTI ID:5290142

Kolibal, J G

The arrangement of the tokamak fusion test reactor diagnostic system results in a number of streaming paths that are directly visible to the plasma. Two important configurations of these penetrations have been examined: the large isolated ducts through the primary igloo shield at the plasma midplane, and the coplaner diagnostic tubes through the substructure beneath the plasma. The spatial distribution of the flux and spectrum has been determined as preliminary input for the design of the diagnostic shield boxes.

• Research Organization: Princeton University, Plasma Physics Laboratory, Princeton, NJ
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 5290142
• Journal Information: Nucl. Technol./Fusion; (United States), Journal Name: Nucl. Technol./Fusion; (United States) Vol. 2:2; ISSN NTFUD
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700102* -- Fusion Energy-- Plasma Research-- Diagnostics
CALCULATION METHODS
DESIGN
DISTRIBUTION
FUNCTIONS
NEUTRONIC DAMAGE FUNCTIONS
PLASMA DIAGNOSTICS
RADIATION FLUX
RADIATION STREAMING
RADIATION TRANSPORT
SHIELDS
SPATIAL DISTRIBUTION
TFTR REACTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS