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.