TFTR remote maintenance
Conference
·
OSTI ID:5256756
The Tokamak Fusion Test Reactor (TFTR) is the first tokamak designed to utilize tritium plasmas and achieve significant neutron yields. Tritium operations are scheduled for the early 1980's at the Princeton Plasma Physics Laboratory. Complex operations of unprecedented scale must be performed remotely. The design of TFTR and the maintenance system supporting it are developing in parallel. The nature of the problem and a proposed set of maintenance tools are described.
- Research Organization:
- Princeton Univ., N.J. (USA). Plasma Physics Lab.
- DOE Contract Number:
- EY-76-C-02-3073
- OSTI ID:
- 5256756
- Report Number(s):
- CONF-771117-4
- Country of Publication:
- United States
- Language:
- English
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·
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
D-T REACTORS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MAINTENANCE
NUCLEI
ODD-EVEN NUCLEI
OPERATION
RADIOISOTOPES
REMOTE HANDLING EQUIPMENT
TFTR REACTOR
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
D-T REACTORS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MAINTENANCE
NUCLEI
ODD-EVEN NUCLEI
OPERATION
RADIOISOTOPES
REMOTE HANDLING EQUIPMENT
TFTR REACTOR
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES