Published 1981 | Version v1
Journal article

U.S. INTOR divertor design

  • 1. Argonne Natl Lab, IL, USA

Description

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

Additional details

Publishing Information

Journal Title
Proc. Symp. Eng. Probl. Fusion Res.
Journal Issue
p. 728-731
Series
Proc. Symp. Eng. Probl. Fusion Res.
ISSN
0145-5958

Conference

Title
9. symposium on engineering problems of fusion research.
Dates
26 - 29 Oct 1981.
Place
Chicago, IL (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
14766271
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
IMPURITIES; INTOR TOKAMAK; POLOIDAL FIELD DIVERTORS; SPECIFICATIONS; STRESSES
Descriptors DEC
CLOSED PLASMA DEVICES; DIVERTORS; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Secondary number(s)
CONF-811040--.