Modelling of tritium retention and target lifetime of the ITER divertor using the ERO code

Key ITER plasma edge and plasma–material interaction issues

G. Federici, P. Andrew, P. Barabaschi et al. · Journal of Nuclear Materials · 2003 · 353 citations

Natural Sciences, Nuclear Engineering, Physics +14

Assessment of erosion of the ITER divertor targets during type I ELMs

G. Federici, A. Loarte, G. Strohmayer · Plasma Physics and Controlled Fusion · 2003 · 342 citations

Engineering, Materials Engineering, Mechanical Engineering +17

Simulation of the plasma-wall interaction in a tokamak with the Monte Carlo code ERO-TEXTOR

A. Kirschner, V. Philipps, J. Winter et al. · Nuclear Fusion · 2000 · 253 citations · Full text

Natural Sciences, Nuclear Engineering, Physics +17

Flux dependence of carbon erosion and implication for ITER

J. Roth, A. Kirschner, W. Bohmeyer et al. · Journal of Nuclear Materials · 2005 · 94 citations

Natural Sciences, Earth Sciences, Carbon Management +11

Modelling of carbon transport in fusion devices: evidence of enhanced re-erosion of in-situ re-deposited carbon

A. Kirschner, P. Wienhold, V. Philipps et al. · Journal of Nuclear Materials · 2004 · 59 citations

Engineering, Earth Sciences, Nuclear Engineering +16