W. M. Shu

ITER tungsten divertor design development and qualification program

Takeshi Hirai, F. Escourbiac, S. Carpentier‐Chouchana et al. · Fusion Engineering and Design · 2013 · 221 citations

Industrial Design, Engineering, Mechanical Engineering +3

Surface morphology and deuterium retention in tungsten exposed to low-energy, high flux pure and helium-seeded deuterium plasmas

V.Kh. Alimov, W. M. Shu, J. Roth et al. · Physica Scripta · 2009 · 130 citations

Engineering, Plasma Science, Plasma Physics +18

Subsurface morphology changes due to deuterium bombardment of tungsten

S. Lindig, M. Balden, V.Kh. Alimov et al. · Physica Scripta · 2009 · 119 citations

Materials Science, Ion Implantation, Engineering +14

Microstructure dependence of deuterium retention and blistering in the near-surface region of tungsten exposed to high flux deuterium plasmas of 38 eV at 315 K

W. M. Shu, A. Kawasuso, Yukio Miwa et al. · Physica Scripta · 2007 · 103 citations

Engineering, Nuclear Physics, Plasma Science +20

Temperature dependence of surface topography and deuterium retention in tungsten exposed to low-energy, high-flux D plasma

V.Kh. Alimov, W. M. Shu, J. Roth et al. · Journal of Nuclear Materials · 2011 · 102 citations

Materials Science, Engineering, Physics +9