U. Stiefel

A hybrid blanket for a reversed-field pinch reactor

S. Pelloni, W. Green, M. Victoria, 1987 .

Development of plasma CVD and feasibility study of boron carbide in-situ coatings for tokamaks

W. Portmann, M. Heintze, S. Vepřek, 1989 .

PIREX II — A new irradiation facility for testing fusion first wall materials

D. Gavillet, M. Victoria, P. Marmy, 1990 .

Recent European research advances in snow loading and their possible implementation in the Eurocodes

Paolo Formichi, R. Del Corso, U Stiefel, 2000 .

Investigation of sub-surface damage during sliding wear of alumina using focused ion-beam milling

P. Munroe, M. Hoffman, U. Stiefel, 2002 .

Friction and wear in the hostile environment of a tokamak

P. Marmy, P. Marmy, U. Stiefel, 1990 .