Zobrazeno 1 - 4
of 4
pro vyhledávání: '"Ulf Ilg"'
Autor:
A. Brožová, M. Postler, J. Kysela, O. Erben, W. Rűhle, H. Hoffmann, G. Brűmmer, Ulf Ilg, M. Ruščák
Publikováno v:
Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::430f0e8c8492352de81445ca0b3df13e
https://doi.org/10.1002/9781118787618.ch92
https://doi.org/10.1002/9781118787618.ch92
Publikováno v:
Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors ISBN: 9783319487601
15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Recent investigations at different laboratories have shown a strong effect of chloride contaminations on the crack growth rate of low-alloy steel (LAS) in oxygenated high-temperature water (HTW). Therefore, a research project was launched to systemat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3f2c01a1c9a1473ba497d92491456f62
https://doi.org/10.1007/978-3-319-48760-1_51
https://doi.org/10.1007/978-3-319-48760-1_51
Publikováno v:
Volume 6: Materials and Fabrication, Parts A and B.
In order to exclude the possibility of catastrophic failure of safety relevant pressure-retaining components in nuclear power plants during operation, the “integrity concept” is applied in Germany. It has been developed over the past 30 years on
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f4b271b2532e17e172d2139a530247b5
https://doi.org/10.1115/pvp2011-57810
https://doi.org/10.1115/pvp2011-57810
Publikováno v:
Volume 6: Materials and Fabrication, Parts A and B.
During the design stage of the today operating German PWRs, one major design target was to manage the materials ageing behavior of the ferritic reactor pressure vessel (RPV) steel in oder to prevent a brittle fracture of the RPV under all possible lo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::949418f173538dc8ba3248e9b7370390
https://doi.org/10.1115/pvp2008-61188
https://doi.org/10.1115/pvp2008-61188