Heat flux depositions on the WEST divertor and first wall components
Description
Highlights: • Heat fluxes up to 20 MW/m2 are required on the divertor of Tore Supra WEST. • Incident heat flux onto the main inner components are simulated with PFCFlux. • Ripple of the magnetic field is accounted for. • Results shows that expected heat fluxes are reachable on the divertor. • Heat flux on the other components is within their limits. - Abstract: The primary goal of the WEST project is to be a test-bed for ITER W divertor components, in terms of manufacturing issues as well as fatigue and lifetime regarding thermal loads during operations. Therefore it is necessary to ensure that the thermal loads available in Tore Supra are of the same magnitude as those expected for ITER. It is also necessary to ensure that the other plasma facing components would not be a limitation to reach this target. On this basis, simulations of the incident heat flux on the main components have been done for different parameters. Those simulations are done with PFCFlux code and include the variation of the toroidal magnetic field called ripple effect. This paper reports the results of those simulations and concludes on the usability of the plasma facing components with the required heat loads.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2014.12.024Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2014.12.024;
- PII
- S0920-3796(14)00668-1;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 98-99
- Journal Page Range
- p. 1294-1298
- 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
- 48006599
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DIVERTORS; FATIGUE; FIRST WALL; HEAT FLUX; HEATING LOAD; ITER TOKAMAK; MANUFACTURING; PLASMA; SERVICE LIFE; SIMULATION; TORE SUPRA TOKAMAK
- Descriptors DEC
- CLOSED PLASMA DEVICES; LIFETIME; MECHANICAL PROPERTIES; 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.