Published October 2015 | Version v1
Journal article

MAST Upgrade – Construction Status

Description

Highlights: • Outlines unique capability of MAST-U, including divertor and diagnostic capability. • Describes progress made in the manufacture and assembly of key MAST-U components. • Highlights the design challenges that have been overcome. • Lists the key lessons learned thus far in the project. - Abstract: The Mega Amp Spherical Tokamak (MAST) is the centre piece of the UK fusion research programme. In 2010, a MAST Upgrade programme was initiated with three primary objectives, to contribute to: (1) testing reactor concepts (in particular exhaust solutions via a flexible divertor allowing Super-X and other extended leg configurations); (2) adding to the knowledge base for ITER (by addressing important plasma physics questions and developing predictive models to help optimise ITER performance of ITER) and (3) exploring the feasibility of using a spherical tokamak as the basis for a fusion Component Test Facility. With the project mid-way through its construction phase, progress will be reported on a number of the critical subsystems. This will include manufacture and assembly of the coils, armour and support structures that make up the new divertors, construction of the new set coils that make up the centre column, installation of the new power supplies for powering the divertor coils and enhanced TF coil set, progress in delivering the upgraded diagnostic capability, the modification and upgrading of the NBI heating systems and the complete overhaul of the machine control infrastructure, including a new control room with full remote participation facilities.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2015.03.002

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2015.03.002;
arXiv
arXiv:1503.06677v1;
PII
S0920-3796(15)00160-X;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
96-97
Journal Page Range
p. 42-47
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
28. symposium on fusion technology
Acronym
SOFT-28
Dates
29 Sep - 3 Oct 2014
Place
San Sebastian (Spain)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
48006339
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BEAM INJECTION HEATING; CONSTRUCTION; CONTROL ROOMS; DIVERTORS; ITER TOKAMAK; KNOWLEDGE BASE; MAST TOKAMAK; NEUTRAL ATOM BEAM INJECTION; PLASMA; POWER SUPPLIES; TEST FACILITIES
Descriptors DEC
BEAM INJECTION; CLOSED PLASMA DEVICES; ELECTRONIC EQUIPMENT; EQUIPMENT; HEATING; PLASMA HEATING; SPHEROMAK DEVICES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Copyright
Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.