Published July 1985 | Version v1
Journal article

Analysis of the key features of the Demountable Tokamak Fusion Core concept

  • 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--.