Crack growth investigations on reactor pressure vessel steels in a running power reactor (BWR)
No abstract available.
URL: https://publications.hereon.de/id/13373/
Authors:Anders, D.,Mueller, W.,Schmitt, F. J.
Year:1989
In: ICCGR Meeting; Fourth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems
Location:Jekyll Island, GA (USA)
Date:August 6-13, 1989
Type:conference lecture
Cite as: Anders, D.; Mueller, W.; Schmitt, F.: Crack growth investigations on reactor pressure vessel steels in a running power reactor (BWR). ICCGR Meeting; Fourth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems. Jekyll Island, GA (USA), 1989.
