Published September 2019 | Version v1
Journal article

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

  • 1. CEA, Institute for Research on Fusion by Magnetic confinement, 13108, Saint-Paul-Lez-Durance (France)
  • 2. Aix Marseille Univ, CNRS, IUSTI, Marseille (France)

Description

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 λqt, power spreading in the private flux region St and the strike point location x0). 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.

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2019.01.074;
PII
S0920379619300821;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
146
Journal Page Range
p. 757-760
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
SOFT-30: 30. Symposium on fusion technology
Acronym
SI
Dates
16-21 Sep 2018
Place
Giardini Naxos, Sicily (Italy)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
55104057
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DIVERTORS; FIRST WALL; HEAT FLUX; HEAT TRANSFER; PLASMA DIAGNOSTICS; THERMOCOUPLES
Descriptors DEC
ENERGY TRANSFER; MEASURING INSTRUMENTS; THERMONUCLEAR REACTOR WALLS

Optional Information

Copyright
Copyright (c) 2019 Elsevier B.V. All rights reserved.
Collaborations
WEST team