In situ observation of tungsten plasma-facing components after the first phase of operation of the WEST tokamak

The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment

J. Bucalossi, M. Missirlian, P. Moreau et al. · Fusion Engineering and Design · 2014 · 229 citations

Natural Sciences, Nuclear Engineering, Fusion Engineering +13

Surface heat loads on the ITER divertor vertical targets

J. Gunn, S. Carpentier‐Chouchana, F. Escourbiac et al. · Nuclear Fusion · 2017 · 196 citations · Full text

Natural Sciences, Nuclear Engineering, Fusion Engineering +16

Design optimization of the ITER tungsten divertor vertical targets

Takeshi Hirai, S. Carpentier‐Chouchana, F. Escourbiac et al. · Fusion Engineering and Design · 2017 · 76 citations

Engineering, Materials Engineering, Nuclear Engineering +14

Tungsten erosion by arcs in ASDEX upgrade

V. Rohde, N. Endstrasser, U. von Toussaint et al. · Journal of Nuclear Materials · 2010 · 57 citations

Natural Sciences, Materials Engineering, Materials Science +10

Erosion and redeposition patterns on entire erosion marker tiles after exposure in the first operation phase of WEST

M. Balden, M. Mayer, B. Bliewert et al. · Physica Scripta · 2021 · 38 citations · Full text

Natural Sciences, Materials Engineering, Materials Science +14