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:journal article,GKSS report
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. Nuclear Engineering and Design. 1992. vol. 136, 265-276.
