U. S. INTOR divertor design

Conference · Wed Dec 31 23:00:00 EST 1980 · Proc. Symp. Eng. Probl. Fusion Res.; (United States)

OSTI ID:6420754

Mattas, R F; Abdou, M A; Brooks, J N; Gohar, Y; Misra, B; Smith, D L.M.; Bowers, D; Delaney, M; Grewing, C O; Morgan, G D

The impurity control system in INTOR is a single null poloidal divertor. The total power to the divertor is 80 MW, primarily in the form of ionized particles that have escaped from the plasma. The ionized particles strike the divertor collector plates, resulting in high surface heating and sputtering that limits the lifetime to approximately 2 yr. This short lifetime means that the plates must be replaced several times during the reactor life, and, therefore, the divertor module has been designed to be replaced independently of the other reactor components. The divertor collector plates have been analyzed in detail, and the results of thermal and stress calculations are presented.

• Research Organization: Argonne Natl Lab, IL, USA
• OSTI ID: 6420754
• Report Number(s): CONF-811040-
• Journal Information: Proc. Symp. Eng. Probl. Fusion Res.; (United States), Journal Name: Proc. Symp. Eng. Probl. Fusion Res.; (United States); ISSN PSERD
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
DESIGN
DIVERTORS
IMPURITIES
INTOR TOKAMAK
POLOIDAL DIVERTORS
STRESSES
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS