Published June 2009 | Version v1
Journal article

ITER vertical stabilization system

  • 1. Associazione Euratom-ENEA-CREATE, DIMET, Universita degli Studi di Napoli (Italy)
  • 2. FUSION FOR ENERGY Joint Undertaking, 08019 Barcelona (Spain)
  • 3. EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon (United Kingdom)
  • 4. Associazione Euratom-ENEA-CREATE, DIMET, Universita degli Studi di Reggio Calabria (Italy)
  • 5. Associazione Euratom-ENEA-CREATE, DIMET, Universita degli Studi di Cassino (Italy)

Description

As part of the ITER design review, a reassessment of the specifications underlying the design of the vertical stabilization system (VS) was performed. Recent results from experiments, aimed at the evaluation of the feasibility of the ITER reference scenarios, have raised several concerns regarding mostly the ramp-up and ramp-down phases of the pulse. The main issue is the value of the internal inductance li which may reach values outside the range 0.7-1, considered as reference for the ITER control system design. Similar concerns apply to the low current L-mode plasmas, needed to the exploitation of the machine towards the development of the 15 MA pulse. The performance of the reference vertical stabilization system, under the revised conditions may be marginal, in particular if the effect of plasma generated noise on the velocity measurement is considered. A reliable and robust VS is mandatory to guarantee the operation of ITER at the reference elongation and plasma current values. To avoid de-scoping of the machine mission, several solutions have been proposed to improve the VS performances, ranging from an upgrade of the maximum voltage available to the present external coils system, to the introduction of in-vessel passive and/or active conductors. The paper presents an overview of the modelling and experimental effort aimed at the assessment of the baseline ITER VS and analyses the proposed solutions to improve the system performance.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2009.01.010

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2009.01.010;
PII
S0920-3796(09)00039-8;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
84
Journal Issue
2-6
Journal Page Range
p. 394-397
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
25. symposium on fusion technology
Acronym
SOFT-25
Dates
15-19 Sep 2008
Place
Rostock (Germany)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
41031145
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTROL SYSTEMS; DESIGN; ITER TOKAMAK; PERFORMANCE; STABILIZATION
Descriptors DEC
CLOSED PLASMA DEVICES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Copyright
Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.