Published September 2021 | Version v1
Journal article

First temperature database achieved with Fiber Bragg Grating sensors in uncooled plasma facing components of the WEST lower divertor

  • 1. CEA, IRFM, Saint-Paul-lez-Durance F-13108 (France)
  • 2. CEA, List, Gif-sur-Yvettes cedex 91191 (France)
  • 3. Aix-Marseille Université, CNRS, IUSTI UMR 7343, Marseille 13013 (France)

Description

Plasma Facing Components (PFCs) temperature measurement is required to ensure safe high power for long pulse tokamak operation and for physics studies. A set of twenty thermocouples (TCs) and four optical fiber temperature sensing probes, each of them including eleven wavelength-multiplexed fiber Bragg gratings (FBGs) written with UV radiation, have been integrated and deployed in the WEST lower divertor. To avoid any thermal erasure occurring above 400 °C, the gratings have been regenerated using a high temperature annealing process. The FBG probes are embedded in tungsten-coated graphite components with no active cooling. The diagnostic was working correctly from the first plasma breakdown achieved in WEST (in 2017) until the first dismantling of the lower divertor three years later (2020). Collected data are sorted by temperature range to investigate the ageing of both PFCs and diagnostics. Measurements obtained with FBGs and TCs are consistent, no long-term drift is reported during the overall period of use. The maximum temperature reported by FBGs in the divertor is 830 °C obtained with 90 MJ of cumulated plasma energy in one pulse. A short but reversible collapse of the Bragg peak (from 5 down to 2 dB) has been observed under high temperature due to the strong temperature gradients measured along the fiber (about 20 °C/mm, for an FBG size of 3 mm). This feedback demonstrates that regenerated FBGs are suitable for long-term temperature monitoring in tokamak environment with high heat load, high temperature and gradient, strong magnetic field and vacuum constraint.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2021.112528

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2021.112528;
PII
S0920379621003045;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
170
Journal Page Range
vp.
ISSN
0920-3796
CODEN
FEDEEE

Optional Information

Copyright
Copyright (c) 2021 Elsevier B.V. All rights reserved.
Collaborations
the WEST team