Cross diagnostics measurements of heat load profiles on the lower tungsten divertor of WEST in L-mode experiments
Author:
Funder
H2020 Euratom
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics
Reference19 articles.
1. The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment
2. Overview of the different processes of tungsten coating implemented into WEST tokamak
3. Flush-mounted Langmuir probes in the WEST tokamak divertor
4. Heat Flux estimation in WEST divertor with embedded thermocouples
5. Integration of fiber Bragg grating temperature sensors in plasma facing components of the WEST tokamak
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1. Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms;Nuclear Materials and Energy;2023-12
2. Infrared detection of tungsten cracking on actively cooled ITER-like component during high power experiment in WEST;Nuclear Materials and Energy;2023-12
3. Surface heat flux estimation with embedded thermocouples and Fiber Bragg Grating sensor in ITER-like plasma facing components;Fusion Engineering and Design;2023-05
4. Calibration methods and uncertainties estimation of WEST infrared thermography diagnostics;Fusion Engineering and Design;2023-05
5. Plasma exposure of a pre-damaged ITER-like plasma facing unit in the WEST tokamak: in-situ and post-mortem measurements;Nuclear Materials and Energy;2023-03
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