Published November 2005 | Version v1
Journal article

The MAST improved divertor

  • 1. EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom)

Description

The Mega Amp Spherical Tokamak (MAST) at Culham is one of the leading world machines studying the spherical tokamak (ST) concept. At the time of the initial construction in 1998 little was known about the sort of divertor structures that would be required in an ST. The machine was therefore provided with relatively rudimentary structures that were designed mostly to protect important components from the hot plasma. While these have served the machine well it was accepted that they might not be suitable when operating MAST to its full potential. The years of experience of operating MAST have led to the design, manufacture and now installation of a new divertor, the MAST improved divertor (MID), that should be able to cope with the full performance of the machine. The design is based on imbricated (fan-shaped) disks of tiles at the top and bottom of the machine for the outer strike points, giving an excellent compromise between power handling and diagnostic access, with substantial new centre column strike point armour and a shaped plate in between. High purity graphite is chosen as the plasma facing material in preference to CFC since in this case it has a better balance of performance and cost. The lower imbricated disk is insulated in alternate sectors for studies of divertor biasing and extensive diagnostics and additional inboard gas injection are included

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2005.06.059;
PII
S0920-3796(05)00053-0;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
75-79
Journal Page Range
p. 285-289
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
23. symposium of fusion technology
Acronym
SOFT 23
Dates
20-24 Sep 2004
Place
Venice (Italy)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
37106430
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DESIGN; DIVERTORS; FIRST WALL; GAS INJECTION; GRAPHITE; HOT PLASMA; MAST TOKAMAK; OPTIMIZATION; PERFORMANCE; PLATES; SPHERICAL CONFIGURATION
Descriptors DEC
CARBON; CLOSED PLASMA DEVICES; CONFIGURATION; ELEMENTS; FLUID INJECTION; MINERALS; NONMETALS; PLASMA; SPHEROMAK DEVICES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TOKAMAK DEVICES

Optional Information

Copyright
Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.