%0 conference lecture
%@ 
%A Anders, D.,Mueller, W.,Schmitt, F. J.

%D 1989
%J ICCGR Meeting; Fourth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems
%N 
%P  

%T Crack growth investigations on reactor pressure vessel steels in a running power reactor (BWR)
%U 
 
%X