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Seifert, H.P., Ritter, S. (2008) Strain-induced corrosion cracking behaviour of low-alloy steels under boiling water reactor conditions. Journal of Nuclear Materials, 378 (3). 312-326 doi:10.1016/j.jnucmat.2008.06.035

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Reference TypeJournal (article/letter/editorial)
TitleStrain-induced corrosion cracking behaviour of low-alloy steels under boiling water reactor conditions
JournalJournal of Nuclear Materials
AuthorsSeifert, H.P.Author
Ritter, S.Author
Year2008 (September)Volume378
Issue3
PublisherElsevier BV
DOIdoi:10.1016/j.jnucmat.2008.06.035Search in ResearchGate
Generate Citation Formats
Mindat Ref. ID4159737Long-form Identifiermindat:1:5:4159737:2
GUID0
Full ReferenceSeifert, H.P., Ritter, S. (2008) Strain-induced corrosion cracking behaviour of low-alloy steels under boiling water reactor conditions. Journal of Nuclear Materials, 378 (3). 312-326 doi:10.1016/j.jnucmat.2008.06.035
Plain TextSeifert, H.P., Ritter, S. (2008) Strain-induced corrosion cracking behaviour of low-alloy steels under boiling water reactor conditions. Journal of Nuclear Materials, 378 (3). 312-326 doi:10.1016/j.jnucmat.2008.06.035
In(2008, September) Journal of Nuclear Materials Vol. 378 (3) Elsevier BV

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Seifert, H.P., Ritter, S. (2008) Stress corrosion cracking of low-alloy reactor pressure vessel steels under boiling water reactor conditions. Journal of Nuclear Materials, 372 (1). 114-131 doi:10.1016/j.jnucmat.2007.03.048
Seifert, H.P., Ritter, S. (2008) Corrosion fatigue crack growth behaviour of low-alloy reactor pressure vessel steels under boiling water reactor conditions. Corrosion Science, 50. 1884-1899 doi:10.1016/j.corsci.2008.03.010
Seifert, H.P., Ritter, S. (2016) The influence of ppb levels of chloride impurities on the strain-induced corrosion cracking and corrosion fatigue crack growth behavior of low-alloy steels under simulated boiling water reactor conditions. Corrosion Science, 108. 148-159 doi:10.1016/j.corsci.2016.03.010
Seifert, H.P., Ritter, S. (2016) The influence of ppb levels of chloride impurities on the stress corrosion crack growth behaviour of low-alloy steels under simulated boiling water reactor conditions. Corrosion Science, 108. 134-147 doi:10.1016/j.corsci.2016.03.001
Ritter, S., Seifert, H.P. (2008) Effect of corrosion potential on the corrosion fatigue crack growth behaviour of low-alloy steels in high-temperature water. Journal of Nuclear Materials, 375 (1). 72-79 doi:10.1016/j.jnucmat.2007.10.010
Seifert, H.P., Ritter, S., Leber, H.J. (2012) Corrosion fatigue crack growth behaviour of austenitic stainless steels under light water reactor conditions. Corrosion Science, 55. 61-75 doi:10.1016/j.corsci.2011.10.005
Seifert, H.P., Ritter, S., Shoji, T., Peng, Q.J., Takeda, Y., Lu, Z.P. (2008) Environmentally-assisted cracking behaviour in the transition region of an Alloy182/SA 508 Cl.2 dissimilar metal weld joint in simulated boiling water reactor normal water chemistry environment. Journal of Nuclear Materials, 378 (2). 197-210 doi:10.1016/j.jnucmat.2008.06.034
Seifert, H.P., Ritter, S., Leber, H.J. (2012) Corrosion fatigue initiation and short crack growth behaviour of austenitic stainless steels under light water reactor conditions. Corrosion Science, 59. 20-34 doi:10.1016/j.corsci.2012.02.008
Bai, Juxing, Ritter, Stefan, Seifert, Hans-Peter, Virtanen, Sannakaisa (2018) Stress corrosion cracking initiation and short crack growth behaviour in Alloy 182 weld metal under simulated boiling water reactor hydrogen water chemistry conditions. Corrosion Science, 131. 208-222 doi:10.1016/j.corsci.2017.11.021
Ritter, S., Seifert, H.P. (2007) Evaluation of the mitigation effect of hydrogen water chemistry in BWRs on the low-frequency corrosion fatigue crack growth in low-alloy steels. Journal of Nuclear Materials, 360 (2). 170-176 doi:10.1016/j.jnucmat.2006.07.023
Heldt, J., Seifert, H.P. (2001) Stress corrosion cracking of low-alloy, reactor-pressure-vessel steels in oxygenated, high-temperature water. Nuclear Engineering and Design, 206 (1). 57-89 doi:10.1016/s0029-5493(00)00381-2
 
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