R.E. Nygren

In-vessel tritium retention and removal in ITER

G. Federici, R.A. Anderl, P. Andrew et al. · Journal of Nuclear Materials · 1999 · 241 citations · Full text

Chemical Engineering, Engineering, Environmental Engineering +4

Physics conclusions in support of ITER W divertor monoblock shaping

R.A. Pitts, S. Bardin, Marcel Berg et al. · Nuclear Materials and Energy · 2017 · 175 citations · Full text

Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI

R.E. Nygren, F.L. Tabarés · Nuclear Materials and Energy · 2016 · 130 citations · Full text

Liquid lithium divertor characteristics and plasma–material interactions in NSTX high-performance plasmas

Michael Jaworski, T. Abrams, Jean Paul Allain et al. · Nuclear Fusion · 2013 · 94 citations

Engineering, Fusion Power, Plasma Science +17

NSTX plasma operation with a Liquid Lithium Divertor

H. Kugel, Jean Paul Allain, M.G. Bell et al. · Fusion Engineering and Design · 2011 · 89 citations

Engineering, Applied Plasma Physic, Plasma Science +3