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G. Vieider

Development of tungsten armor and bonding to copper for plasma-interactive components
1998 · I Smid, M Akiba, et al. · Journal of Nuclear Materials · 331
Critical heat flux analysis and R&D for the design of the ITER divertor
1999 · A.R. Raffray, J. Schlosser, et al. · Fusion Engineering and Design · 153
Armor and heat sink materials joining technologies development for ITER plasma facing components
2000 · V Barabash, M Akiba, et al. · Journal of Nuclear Materials · 69
Selection, development and characterisation of plasma facing materials for ITER
1996 · V. Barabash, M. Akiba, et al. · Journal of Nuclear Materials · 56
Lifetime of Be-, CFC- and W-armoured ITER divertor plates
1996 · I. Šmid, H.D. Pacher, et al. · Journal of Nuclear Materials · 53
ITER divertor, design issues and research and development
1999 · R. Tivey, T. Ando, et al. · Fusion Engineering and Design · 48
Erosion lifetime of ITER divertor plates
1997 · H.D. Pacher, I. Smid, et al. · Journal of Nuclear Materials · 46
Next European Torus In-Vessel Components
1988 · Max Chazalon, Jean-Louis Boutard, et al. · Fusion Technology · 41
European achievements for ITER high heat flux components
2001 · M Merola, G Vieider, et al. · Fusion Engineering and Design · 35
Carbon fiber composites application in ITER plasma facing components
1998 · V Barabash, M Akiba, et al. · Journal of Nuclear Materials · 32
ITER plasma facing components, design and development
1991 · G. Vieider, A. Cardella, et al. · Fusion Engineering and Design · 29
On the use of flat tile armour in high heat flux components
1998 · M. Merola, G. Vieider · Journal of Nuclear Materials · 27
Manufacturing and testing of a prototypical divertor vertical target for ITER
2000 · M Merola, L Plöchl, et al. · Journal of Nuclear Materials · 26
European development of the ITER divertor target
1999 · G Vieider, M Merola, et al. · Fusion Engineering and Design · 26
Comparison between various thermal hydraulic tube concepts for the ITER divertor
1997 · I. Smid, J. Schlosser, et al. · Elsevier eBooks · 26
Neutron irradiation effects on the properties of carbon materials
1994 · C.H. Wu, J.P. Bonal, et al. · Journal of Nuclear Materials · 25
Conceptual design of the dual-coolant blanket within the framework of the EU power plant conceptual study (TW2-TRP-PPCS12). Final report
2003 · Norajitra, P., Bühler, L., et al. · Repository KITopen (Karlsruhe Institute of Technology) · 24
Neutron-irradiation effects on high heat flux components – examination of plasma-facing materials and their joints
2000 · M Rödig, R Conrad, et al. · Journal of Nuclear Materials · 24
Overview of the EU small scale mock-up tests for ITER high heat flux components
1998 · G Vieider, V Barabash, et al. · Fusion Engineering and Design · 24
EU results on neutron effects on PFC materials
1998 · C.H. Wu, J.P. Bonal, et al. · Fusion Engineering and Design · 23
Reference testing of actively cooled mock-ups for the neutron-irradiation experiments PARIDE 3 and 4
2001 · M Rödig, R Duwe, et al. · Fusion Engineering and Design · 22
Overview of EU CFCs development for plasma facing materials
1998 · C.H Wu, C Alessandrini, et al. · Journal of Nuclear Materials · 20
European development of prototypes for ITER high heat flux components
2000 · G Vieider, M Merola, et al. · Fusion Engineering and Design · 18
Safety and Environmental Assessment of Fusion Power (SEAFP) Final Report of the SEAFP Project
1995 · J. Raeder, I. Cook, et al. · PORTO@Iris · 17
Net plasma facing components
1989 · G. Vieider, M. Harrison, et al. · Fusion Engineering and Design · 16
Works count: 101
Citation count: 1,492
H-index: 21
I10-index: 33
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