Published 1976
| Version v1
Report
Tokamak Engineering Technology Facility
Description
The Tokamak Engineering Technology Facility (TETF) is a neutral beam driven D-T machine with a major radius (R) of 3 m and a plasma current (I/sub p/) of 1.4 MA based on the counterstreaming-ion-torus mode of operation. It can be used to demonstrate fusion reactor technology required for the Experimental Power Reactor and to serve as a radiation test facility
Additional details
Additional titles
- Augmented title (English)
- Plasma physics and reactor performance
Publishing Information
- Imprint Title
- Technology of controlled nuclear fusion. Volume I
- Journal Page Range
- p. 95-105.
- Report number
- CONF-760935--P1
Conference
- Title
- 2. topical meeting on the technology of controlled nuclear fusion.
- Dates
- 21 Sep 1976.
- Place
- Richland, Washington, United States of America (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8333655
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- MATERIALS HANDLING; MATERIALS TESTING; SPECIFICATIONS; SUPERCONDUCTING MAGNETS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TRITIUM
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; ELECTRICAL EQUIPMENT; ELECTROMAGNETS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; MAGNETS; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; SUPERCONDUCTING DEVICES; TESTING; THERMONUCLEAR DEVICES; YEARS LIVING RADIOISOTOPES