Analysis of the key features of the Demountable Tokamak Fusion Core concept
Creators
- 1. Energy Applications and Systems Inc., Del Mar, CA
Description
The Demountable Tokamak Fusion Core (DTFC) concept is a water-cooled, normally conducting tokamak provided with joints in the toroidal field coil turns. These joints, located in the top and bottom horizontal members of each turn, permit the removal and replacement of the core of the tokamak (central OH coil, vacuum vessel, impurity control system, RF heating and current drive systems, inner blanket, and PF trimming coils). The rest of the tokamak (outer blanket, toroidal field current return coils, and main PF coils) remains in-place. This feature arises because the DTFC was conceived in recognition of the fact the core of the tokamak is directly exposed to fusion neutron and charged particle radiation and is the subsystem that will fail first. Provision for the replacement of the core in a straightforward way will significantly increase the availability of a DTFC facility for engineering and commercial applications
Additional details
Publishing Information
- Journal Title
- Fusion Technol.
- Journal Volume
- 8
- Journal Issue
- 1
- Series
- Fusion Technol.
- Journal Page Range
- 1339-1344
- ISSN
- 0748-1896
- CODEN
- FUSTE
Conference
- Title
- 6. topical meeting on the technology of fusion energy.
- Dates
- 3-7 Mar 1985.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17075221
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ELECTROMAGNETS; JOINTS; MAGNET COILS; MAINTENANCE; MODULAR STRUCTURES; SEPARATION PROCESSES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELECTRIC COILS; ELECTRICAL EQUIPMENT; EQUIPMENT; MAGNETS; THERMONUCLEAR DEVICES
Optional Information
- Secondary number(s)
- CONF-850310--.