The development of safe high current operation in JET-ILW
Creators
- 1. CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom)
- 2. Instituto de Plasmas e Fusão Nuclear, IST, Universidade de Lisboa (Portugal)
- 3. Associazione EURATOM-ENEA sulla Fusione, Consorzio RFX Padova (Italy)
- 4. Max-Planck-Institut für Plasmaphysik, 85748 Garching (Germany)
- 5. IRFM-CEA, Centre de Cadarache, 13108 Sant-Paul-lez-Durance (France)
- 6. Fusion for Energy, 08019 Barcelona (Spain)
- 7. IEK-4, Forschungszentrum Jüulich GmbH, Partner in the Trilateral Euregio Cluster, Juelich (Germany)
Description
Highlights: • JET is unique in its capability to operate in DT and at high plasma current. • Studies of high current H-mode are integral part of JET ITER-like Wall programme. • Focus is on safety wrt transient & steady-state heat loads on ILW components. • Early real-time detection of off-normal events and disruption effects mitigation. • This work successfully delivered H-mode scenario up to 4 MA. - Abstract: The JET tokamak is unique amongst present fusion devices in its capability to operate at high plasma current, providing the closest plasma parameters to ITER. The physics benefits of high current operation have to be balanced against the risks to the integrity of the machine due to high force disruptions. The installation of the ITER-Like Wall (ILW) has added risks due to the thermal characteristics of the metal Plasma Facing Components. This paper describes the operational aspects of the scientific development of high current H-mode plasmas with the ILW, focusing on disruption prediction, avoidance and amelioration. The development yielded baseline H-mode plasmas up to 4 MA/3.74 T, comparable to the maximum current achieved in JET in Carbon-Wall (CFC) conditions with similar divertor geometry.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2015.01.014Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2015.01.014;
- PII
- S0920-3796(15)00032-0;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 96-97
- Journal Page Range
- p. 165-170
- 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
- 48006359
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CARBON; DIVERTORS; ELECTRIC CURRENTS; FIRST WALL; HAZARDS; HEATING LOAD; H-MODE PLASMA CONFINEMENT; ITER TOKAMAK; JET TOKAMAK; METALS; PLASMA; SAFETY; STEADY-STATE CONDITIONS; TRANSIENTS
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONFINEMENT; CURRENTS; ELEMENTS; MAGNETIC CONFINEMENT; NONMETALS; PLASMA CONFINEMENT; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Copyright
- Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.