Sustained W-melting experiments on actively cooled ITER-like plasma facing unit in WEST

Very High-Resolution Infrared imagery of misaligned tungsten monoblock edge heating in the WEST tokamak

(2021) A. Grosjean 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

Resolidification-controlled melt dynamics under fast transient tokamak plasma loads

(2020) Svetlana Ratynskaia 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

First heat flux estimation in the lower divertor of WEST with embedded thermal measurements

(2019) J. Gaspar 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

A study of planar toroidal-poloidal beveling of monoblocks on the ITER divertor outer vertical target

(2019) James Paul Gunn et al.   NUCLEAR FUSION

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

Experiments on transient melting of tungsten by ELMs in ASDEX Upgrade

(2018) K. Krieger et al.   NUCLEAR FUSION

WEST regular in-vessel Inspections with the Articulated Inspection Arm robot

(2018) V. Bruno et al.   FUSION ENGINEERING AND DESIGN

Transient induced tungsten melting at the Joint European Torus (JET)

(2017) J W Coenen et al.   PHYSICA SCRIPTA

Methodology for heat flux investigation on leading edges using infrared thermography

(2016) Y. Corre et al.   NUCLEAR FUSION

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: PFC shaping solutions investigated for the ITER-like W divertor

(2013) 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

The heat removal capability of actively cooled plasma-facing components for the ITER divertor

(2011) M Missirlian et al.   PHYSICA SCRIPTA