Published 1987 | Version v1
Book Metadata-only

Ex-vessel remote maintenance for the Compact Ignition Tokamak

Creators

  • 1. Oak Ridge National Lab., P.O. Box X, Oak Ridge, TN (USA)

Description

The authors discuss how the use of deuterium-tritium (D-T) fuel for operation of the Compact Ignition Tokamak (CIT) requires the use of remote handling technology to carry out maintenance operations on the machine. These operations consist in removing and repairing such components as diagnostic modules by using remotely operated maintenance equipment. The major equipment being developed for maintenance external to the plasma chamber includes a bridge-mounted manipulator system for test cell operation, decontamination (decon) equipment, hot cell equipment, and solid-radiation-waste-handling equipment

Additional details

Publishing Information

Publisher
IEEE Service Center.
Imprint Place
Piscataway, NJ (USA)
Imprint Title
Proceedings of the 12th symposium on fusion engineering
Imprint Pagination
vp.
Journal Page Range
p. 756-759.

Conference

Title
12. symposium on fusion engineering.
Dates
12-16 Oct 1987.
Place
Monterey, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
21033661
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPACT IGNITION TOKAMAK; MAINTENANCE; RADIATION PROTECTION; REMOTE HANDLING; REMOTE HANDLING EQUIPMENT; RESEARCH PROGRAMS
Descriptors DEC
CLOSED PLASMA DEVICES; EQUIPMENT; MATERIALS HANDLING EQUIPMENT; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Secondary number(s)
CONF-871007--.