Plasma exposure of a pre-damaged ITER-like plasma facing unit in the WEST tokamak: in-situ and post-mortem measurements
Published 2023 View Full Article
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Title
Plasma exposure of a pre-damaged ITER-like plasma facing unit in the WEST tokamak: in-situ and post-mortem measurements
Authors
Keywords
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Journal
Nuclear Materials and Energy
Volume 34, Issue -, Pages 101366
Publisher
Elsevier BV
Online
2023-01-21
DOI
10.1016/j.nme.2023.101366
References
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Related references
Note: Only part of the references are listed.- Leading edge cracking observed in WEST
- (2022) A Durif et al. PHYSICA SCRIPTA
- Thermal loads in gaps between ITER divertor monoblocks: first lessons learnt from WEST
- (2021) J.P. Gunn et al. Nuclear Materials and Energy
- Cross diagnostics measurements of heat load profiles on the lower tungsten divertor of WEST in L-mode experiments
- (2021) N. Fedorczak et al. Nuclear Materials and Energy
- Interpretation of temperature distribution observed on W-ITER-like PFUs in WEST monitored with a very-high-resolution IR system
- (2021) A. Grosjean et al. FUSION ENGINEERING AND DESIGN
- Divertor power loads and scrape off layer width in the large aspect ratio full tungsten tokamak WEST
- (2021) J. Gaspar et al. NUCLEAR FUSION
- In situ observation of tungsten plasma-facing components after the first phase of operation of the WEST tokamak
- (2021) M. Diez et al. NUCLEAR FUSION
- Erosion and redeposition patterns on entire erosion marker tiles after exposure in the first operation phase of WEST
- (2021) M Balden et al. PHYSICA SCRIPTA
- First plasma exposure of a pre-damaged ITER-like plasma facing unit in the WEST tokamak: procedure for the PFU preparation and lessons learnt
- (2021) Marianne Richou et al. NUCLEAR FUSION
- Sustained W-melting experiments on actively cooled ITER-like plasma facing unit in WEST
- (2021) Y Corre et al. PHYSICA SCRIPTA
- The very high spatial resolution infrared thermography on ITER-like tungsten monoblocks in WEST Tokamak
- (2019) M. Houry et al. FUSION ENGINEERING AND DESIGN
- Emissivity measurement of tungsten plasma facing components of the WEST tokamak
- (2019) J. Gaspar et al. FUSION ENGINEERING AND DESIGN
- Design optimization of the ITER tungsten divertor vertical targets
- (2018) T. Hirai et al. FUSION ENGINEERING AND DESIGN
- Visible spectroscopy diagnostics for tungsten source assessment in the WEST tokamak: First measurements
- (2018) O. Meyer et al. REVIEW OF SCIENTIFIC INSTRUMENTS
- Measurements and controls implementation for WEST
- (2017) P. Moreau et al. FUSION ENGINEERING AND DESIGN
- Material testing facilities and programs for plasma-facing component testing
- (2017) Ch. Linsmeier et al. NUCLEAR FUSION
- Methodology for heat flux investigation on leading edges using infrared thermography
- (2016) Y. Corre et al. NUCLEAR FUSION
- The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment
- (2014) J. Bucalossi et al. FUSION ENGINEERING AND DESIGN
- The WEST project: Current status of the ITER-like tungsten divertor
- (2014) M. Missirlian et al. FUSION ENGINEERING AND DESIGN
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