Published January 1990
| Version v1
Report
Method of helium removal from tokamak reactor discharge chamber
Creators
- 1. Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (USSR). Inst. Atomnoj Ehnergii
Description
The paper describes a new method of helium removal from tokamak plasma by generation between the divertor plates and chamber first wall a screening layer of low-temperature plasma which would ionize and trap neutral atoms. The removal of these atoms out of the chamber could be realized with special pump-limiters. (author). 2 refs, 4 figs
Additional details
Publishing Information
- Imprint Title
- Impurity control in toroidal devices
- Imprint Pagination
- 173 p.
- Journal Page Range
- p. 49-53.
- Report number
- IAEA-TECDOC--536
Conference
- Title
- Technical committee on impurity control.
- Dates
- 13-15 Feb 1989.
- Place
- Naka-Gun (Japan).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 21029571
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HELIUM ASH; POLOIDAL FIELD DIVERTORS; PUMPED LIMITERS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES
- Descriptors DEC
- CHARGED PARTICLES; CLOSED PLASMA DEVICES; DIVERTORS; HELIUM IONS; IONS; LIMITERS; THERMONUCLEAR DEVICES