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Hänninen, Hannu, Aaltonen, Pertti, Rintamaa, Rauno, Arilahti, Esko, Ehrnstén, Ulla (1992) Static and cyclic crack growth of low alloy steels in high-oxygen water simulating HDR test conditions. Nuclear Engineering and Design, 137 (3). 291-304 doi:10.1016/0029-5493(92)90252-q

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Reference TypeJournal (article/letter/editorial)
TitleStatic and cyclic crack growth of low alloy steels in high-oxygen water simulating HDR test conditions
JournalNuclear Engineering and Design
AuthorsHänninen, HannuAuthor
Aaltonen, PerttiAuthor
Rintamaa, RaunoAuthor
Arilahti, EskoAuthor
Ehrnstén, UllaAuthor
Year1992 (November)Volume137
Issue3
PublisherElsevier BV
DOIdoi:10.1016/0029-5493(92)90252-qSearch in ResearchGate
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Mindat Ref. ID10506075Long-form Identifiermindat:1:5:10506075:0
GUID0
Full ReferenceHänninen, Hannu, Aaltonen, Pertti, Rintamaa, Rauno, Arilahti, Esko, Ehrnstén, Ulla (1992) Static and cyclic crack growth of low alloy steels in high-oxygen water simulating HDR test conditions. Nuclear Engineering and Design, 137 (3). 291-304 doi:10.1016/0029-5493(92)90252-q
Plain TextHänninen, Hannu, Aaltonen, Pertti, Rintamaa, Rauno, Arilahti, Esko, Ehrnstén, Ulla (1992) Static and cyclic crack growth of low alloy steels in high-oxygen water simulating HDR test conditions. Nuclear Engineering and Design, 137 (3). 291-304 doi:10.1016/0029-5493(92)90252-q
In(1992, November) Nuclear Engineering and Design Vol. 137 (3) Elsevier BV

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Aaltonen, Pertti, Rintamaa, Rauno, Hänninen, Hannu, Ehrnstén, Ulla, Arilahti, Esko (1993) Cyclic crack growth evaluation of a 20MnMoNi55 piping steel in high-oxygen reactor water. Nuclear Engineering and Design, 144 (1). 111-122 doi:10.1016/0029-5493(93)90013-y
Törrönen, Kari, Wallin, Kim, Saario, Timo, Hänninen, Hannu, Rintamaa, Rauno, Forstén, Jarl (1985) Optimization of metallurgical variables in fracture prevention. Nuclear Engineering and Design, 87. 225-237 doi:10.1016/0029-5493(85)90111-6
Anders, D., Föhl, J. (1992) 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, 136 (3). 265-276 doi:10.1016/0029-5493(92)90028-t
Kussmaul, K., Iskluth, B. (1990) Environmentally assisted crack growth in a low alloy boiler steel in high temperature water containing oxygen. Nuclear Engineering and Design, 119 (2). 415-430 doi:10.1016/0029-5493(90)90181-v
Higuchi, Makoto, Iida, Kunihiro (1991) Fatigue strength correction factors for carbon and low-alloy steels in oxygen-containing high-temperature water. Nuclear Engineering and Design, 129 (3). 293-306 doi:10.1016/0029-5493(91)90138-8
Wolf, L., Häfner, W., Geiss, M., Hansjosten, E., Katzenmeier, G. (1992) Results of HDR-experiments for pipe loads under thermally stratified flow conditions. Nuclear Engineering and Design, 137 (3). 387-404 doi:10.1016/0029-5493(92)90262-t
Smith, E., Griesbach, T.J. (1992) Predicting crack arrest in reactor pressure vessels. Nuclear Engineering and Design, 137 (3). 305-314 doi:10.1016/0029-5493(92)90253-r
(1992) Erratum. Nuclear Engineering and Design, 132 (3). 449pp. doi:10.1016/0029-5493(92)90245-q
Wallin, Kim, Valo, Matti, Rintamaa, Rauno, Törrönen, Kari, Ahlstrand, Ralf (1995) Descriptive characteristics of different types of test for irradiation embrittlement. Nuclear Engineering and Design, 159 (1). 69-80 doi:10.1016/0029-5493(95)01054-l
Kussmaul, Karl (1992) Preface. Nuclear Engineering and Design, 137 (3). doi:10.1016/0029-5493(92)90250-y
(1992) Contents of Volume 137. Nuclear Engineering and Design, 137 (3). 467-470 doi:10.1016/0029-5493(92)90269-2
 
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