Geometry and expected performance of the solid tungsten outer divertor row in JET
- 1. FOM Rijnhuizen, EURATOM Association, Trilateral Euregio Cluster, Nieuwegein (Netherlands)
- 2. IEF-4, Forschungszentrum Juelich, EURATOM Association, Trilateral Euregio Cluster, Juelich (Germany)
- 3. JET-EFDA, Culham Science Centre, Abingdon (United Kingdom)
- 4. IEF-2, Forschungszentrum Juelich, EURATOM Association, Trilateral Euregio Cluster, Juelich Germany (Germany)
- 5. Euratom/UKAEA Fusion Association, Culham Science Centre, Abingdon (United Kingdom)
Description
At JET new plasma-facing components for the main chamber wall and the divertor are being designed and built to mimic the expected ITER plasma wall conditions in the deuterium-tritium operation phase. The main wall elements at JET will be made of beryllium and the divertor plasma-facing surface will be made of tungsten. Most of the divertor tiles will consist of tungsten-coated Carbon Fibre Composite (CFC) material. However one toroidal row in the outer divertor will be made of solid, inertially cooled tungsten. The geometry of these solid tungsten divertor components is optimized within the boundary conditions of the interfaces and the constraints given by the electrodynamical forces. Shadowing calculations as well as rough field line penetration analysis is used to define the geometry of the tungsten lamella stacks. These calculations are based on a set of magnetic equilibria reflecting the operation domain of current JET plasma scenarios. All edges in poloidal and toroidal direction are shadowed to exclude near perpendicular field line impact. In addition, the geometry of the divertor structure is being optimized so that the fraction of the plasma wetted surface is maximised. On the basis of the optimized divertor geometry, performance calculations are done with the help of ANSYS to assess the maximum power exhaust possible with this inertially cooled divertor row.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2009.08.009Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2009.08.009;
- PII
- S0920-3796(09)00256-7;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 85
- Journal Issue
- 2
- Journal Page Range
- p. 153-160
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 41069280
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- CARBON FIBERS; DEUTERIUM; DIVERTORS; FIRST WALL; GEOMETRY; ITER TOKAMAK; JET TOKAMAK; PERFORMANCE; TRITIUM; TUNGSTEN
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; ELEMENTS; FIBERS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; MATHEMATICS; METALS; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; RADIOISOTOPES; REFRACTORY METALS; STABLE ISOTOPES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENTS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.