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First heat flux estimation in the lower divertor of WEST with embedded thermal measurements.

Authors :
Gaspar, J.
Corre, Y.
Firdaouss, M.
Gardarein, J.L.
Gerardin, J.
Gunn, J.P.
Houry, M.
Laffont, G.
Loarer, T.
Missirlian, M.
Morales, J.
Moreau, P.
Pocheau, C.
Tsitrone, E.
Source :
Fusion Engineering & Design. Sep2019:Part A, Vol. 146, p757-760. 4p.
Publication Year :
2019

Abstract

The present paper deals with the surface heat flux estimation with thermocouples (TC) and fiber Bragg grating (FBG) embedded in the plasma facing components (PFC) of the WEST tokamak. A 2D heat transfer model combined with the conjugate gradient method and the adjoint state is used to estimate the plasma heat flux deposited on the PFC. The plasma heat flux is characterized by the time evolution of its amplitude and spatial shape on the target (heat flux decay length λ q t , power spreading in the private flux region S t and the strike point location x 0). As a first step, five ohmic pulses have been investigated with different magnetic configuration and divertor X-point height varying from 44 to 68 mm from the surface. Despite an outboard shift, the relative displacements of the outer strike point as well as the heat flux decay length derived from the TC/FBG systems are consistent with the magnetic equilibrium reconstruction. [ABSTRACT FROM AUTHOR]

Details

Language :
English
ISSN :
09203796
Volume :
146
Database :
Academic Search Index
Journal :
Fusion Engineering & Design
Publication Type :
Academic Journal
Accession number :
138152435
Full Text :
https://doi.org/10.1016/j.fusengdes.2019.01.074