Published 1981
| Version v1
Journal article
U.S. INTOR divertor design
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--.