Testing of ITER-grade Plasma Facing Units in the WEST tokamak: progress in understanding heat loading and damage mechanisms
Published 2023 View Full Article
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Title
Testing of ITER-grade Plasma Facing Units in the WEST tokamak: progress in understanding heat loading and damage mechanisms
Authors
Keywords
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Journal
Nuclear Materials and Energy
Volume -, Issue -, Pages 101546
Publisher
Elsevier BV
Online
2023-11-01
DOI
10.1016/j.nme.2023.101546
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Note: Only part of the references are listed.- Surface heat flux estimation with embedded thermocouples and Fiber Bragg Grating sensor in ITER-like plasma facing components
- (2023) Y. Anquetin et al. FUSION ENGINEERING AND DESIGN
- Plasma exposure of a pre-damaged ITER-like plasma facing unit in the WEST tokamak: in-situ and post-mortem measurements
- (2023) Yann Corre et al. Nuclear Materials and Energy
- Manufacturing, testing and installation of the full tungsten actively cooled ITER-like divertor in the WEST tokamak
- (2023) M. Missirlian et al. FUSION ENGINEERING AND DESIGN
- Overview of the emissivity measurements performed in WEST: in-situ and post-mortem observations
- (2022) Jonathan Gaspar et al. NUCLEAR FUSION
- T-REX: Numerical tool for tungsten damage assessment for DEMO
- (2022) A. Durif et al. JOURNAL OF NUCLEAR MATERIALS
- The MEMOS-U code description of macroscopic melt dynamics in fusion devices
- (2021) E Thorén et al. PLASMA PHYSICS AND CONTROLLED FUSION
- Very High-Resolution Infrared imagery of misaligned tungsten monoblock edge heating in the WEST tokamak
- (2021) A. Grosjean et al. Nuclear Materials and Energy
- 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
- 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
- Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation
- (2021) Jerome B Bucalossi NUCLEAR FUSION
- 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
- Resolidification-controlled melt dynamics under fast transient tokamak plasma loads
- (2020) Svetlana Ratynskaia et al. NUCLEAR FUSION
- First analysis of the misaligned leading edges of ITER-like plasma facing units using a very high resolution infrared camera in WEST
- (2020) A. Grosjean et al. NUCLEAR FUSION
- In-situ assessment of the emissivity of tungsten plasma facing components of the WEST tokamak
- (2020) J. Gaspar et al. Nuclear Materials and Energy
- Infrared thermography in metallic environments of WEST and ASDEX Upgrade
- (2020) M-H. Aumeunier et al. Nuclear Materials and Energy
- Full coverage infrared thermography diagnostic for WEST machine protection
- (2019) X. Courtois et al. FUSION ENGINEERING AND DESIGN
- The very high spatial resolution infrared thermography on ITER-like tungsten monoblocks in WEST Tokamak
- (2019) M. Houry et al. FUSION ENGINEERING AND DESIGN
- Cracks avoidance with a modified solid tungsten divertor in ASDEX Upgrade
- (2018) I. Zammuto et al. FUSION ENGINEERING AND DESIGN
- Design optimization of the ITER tungsten divertor vertical targets
- (2018) T. Hirai et al. FUSION ENGINEERING AND DESIGN
- Experiments on transient melting of tungsten by ELMs in ASDEX Upgrade
- (2018) K. Krieger et al. NUCLEAR FUSION
- Integration of fiber Bragg grating temperature sensors in plasma facing components of the WEST tokamak
- (2018) Y. Corre et al. REVIEW OF SCIENTIFIC INSTRUMENTS
- Surface heat loads on the ITER divertor vertical targets
- (2017) J.P. Gunn et al. NUCLEAR FUSION
- Heat flux depositions on the WEST divertor and first wall components
- (2015) M. Firdaouss et al. FUSION ENGINEERING AND DESIGN
- ELM induced tungsten melting and its impact on tokamak operation
- (2015) J.W. Coenen et al. JOURNAL OF NUCLEAR MATERIALS
- 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
- Status of the ITER full-tungsten divertor shaping and heat load distribution analysis
- (2014) S Carpentier-Chouchana et al. PHYSICA SCRIPTA
- Investigation of steady-state tokamak issues by long pulse experiments on Tore Supra
- (2009) G. Giruzzi et al. NUCLEAR FUSION
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