Divertor power loads and scrape off layer width in the large aspect ratio full tungsten tokamak WEST
Published 2021 View Full Article
- Home
- Publications
- Publication Search
- Publication Details
Title
Divertor power loads and scrape off layer width in the large aspect ratio full tungsten tokamak WEST
Authors
Keywords
-
Journal
NUCLEAR FUSION
Volume 61, Issue 9, Pages 096027
Publisher
IOP Publishing
Online
2021-07-28
DOI
10.1088/1741-4326/ac1803
References
Ask authors/readers for more resources
Related references
Note: Only part of the references are listed.- 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
- Infra-red thermography estimate of deposited heat load dynamics on the lower tungsten divertor of WEST
- (2020) N Fedorczak et al. PHYSICA SCRIPTA
- Inverse radiation problem with infrared images to monitor plasma-facing components temperature in metallic fusion devices
- (2020) Charly Talatizi et al. FUSION ENGINEERING AND DESIGN
- In-situ assessment of the emissivity of tungsten plasma facing components of the WEST tokamak
- (2020) J. Gaspar et al. Nuclear Materials and Energy
- Flush-mounted Langmuir probes in the WEST tokamak divertor
- (2020) R. Dejarnac et al. FUSION ENGINEERING AND DESIGN
- Infrared thermography in metallic environments of WEST and ASDEX Upgrade
- (2020) M-H. Aumeunier et al. Nuclear Materials and Energy
- First heat flux estimation in the lower divertor of WEST with embedded thermal measurements
- (2019) J. Gaspar et al. FUSION ENGINEERING AND DESIGN
- Full coverage infrared thermography diagnostic for WEST machine protection
- (2019) X. Courtois 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
- Integration of fiber Bragg grating temperature sensors in plasma facing components of the WEST tokamak
- (2018) Y. Corre et al. REVIEW OF SCIENTIFIC INSTRUMENTS
- Equilibrium reconstruction at JET using Stokes model for polarimetry
- (2018) Blaise Faugeras et al. NUCLEAR FUSION
- Divertor power load studies for attached L-mode single-null plasmas in TCV
- (2017) R. Maurizio et al. NUCLEAR FUSION
- Heat flux depositions on the WEST divertor and first wall components
- (2015) M. Firdaouss et al. FUSION ENGINEERING AND DESIGN
- WEST Physics Basis
- (2015) C. Bourdelle et al. NUCLEAR FUSION
- The WEST project: Current status of the ITER-like tungsten divertor
- (2014) M. Missirlian et al. FUSION ENGINEERING AND DESIGN
- Empiricial scaling of inter-ELM power widths in ASDEX Upgrade and JET
- (2013) T. Eich et al. JOURNAL OF NUCLEAR MATERIALS
- Outer target heat fluxes and power decay length scaling in L-mode plasmas at JET and AUG
- (2013) A. Scarabosio et al. JOURNAL OF NUCLEAR MATERIALS
Publish scientific posters with Peeref
Peeref publishes scientific posters from all research disciplines. Our Diamond Open Access policy means free access to content and no publication fees for authors.
Learn MoreBecome a Peeref-certified reviewer
The Peeref Institute provides free reviewer training that teaches the core competencies of the academic peer review process.
Get Started