Thermal loads in gaps between ITER divertor monoblocks: first lessons learnt from WEST

First evidence of optical hot spots on ITER-like plasma facing units in the WEST tokamak

(2020) Mathilde Diez et al.   NUCLEAR FUSION

The Commissioning of the WEST Tokamak: Experience and Lessons Learned

(2020) P. Moreau et al.   IEEE TRANSACTIONS ON PLASMA SCIENCE

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

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

(2019) J. Gaspar et al.   FUSION ENGINEERING AND DESIGN

Assessment of critical heat flux margins on tungsten monoblocks of the ITER divertor vertical targets

(2019) F. Escourbiac 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

Design optimization of the ITER tungsten divertor vertical targets

(2018) T. Hirai 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

Impact of tungsten recrystallization on ITER-like components for lifetime estimation

(2018) A. Durif et al.   FUSION ENGINEERING AND DESIGN

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

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

Fracture modes of ITER tungsten divertor monoblock under stationary thermal loads

(2017) S. Panayotis et al.   FUSION ENGINEERING AND DESIGN

Surface heat loads on the ITER divertor vertical targets

(2017) J.P. Gunn et al.   NUCLEAR FUSION

Microstructure and tensile properties of tungsten at elevated temperatures

(2016) Tielong Shen et al.   JOURNAL OF NUCLEAR MATERIALS

Interpretation of the deep cracking phenomenon of tungsten monoblock targets observed in high-heat-flux fatigue tests at 20 MW/m 2

(2015) Muyuan Li et al.   FUSION ENGINEERING AND DESIGN

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

Qualification and post-mortem characterization of tungsten mock-ups exposed to cyclic high heat flux loading

(2013) G. Pintsuk et al.   FUSION ENGINEERING AND DESIGN

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

(2012) M. Rieth et al.   JOURNAL OF NUCLEAR MATERIALS

A magnetically driven reciprocating probe for tokamak scrape-off layer measurements

(2011) J. P. Gunn et al.   REVIEW OF SCIENTIFIC INSTRUMENTS

Thermal shock characterization of tungsten deformed in two orthogonal directions

(2010) G. Pintsuk et al.   JOURNAL OF NUCLEAR MATERIALS

Cracking failure study of ITER-reference tungsten grade under single pulse thermal shock loads at elevated temperatures

(2009) T. Hirai et al.   JOURNAL OF NUCLEAR MATERIALS