Investigation on cyclic crack growth behaviour of reactor pressure vessel steels placed and loaded in the core region of an operating boiling water reactor
No abstract available.
URL: https://publications.hereon.de/id/11863/
Authors:Anders, D., Foehl, J.
Year:1992
In: Nuclear Engineering and Design
Volume:136
Pages: 265-276
Type:Journalpaper
ISSN: 0029-5493
Cite as: Anders, D.; Foehl, J.: Investigation on cyclic crack growth behaviour of reactor pressure vessel steels placed and loaded in the core region of an operating boiling water reactor. In: Nuclear Engineering and Design. Vol. 136 (1992) 265-276.
