Published October 2015 | Version v1
Journal article

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.2014.12.024

Additional 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.