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Role of mean stress on fatigue behavior of a 316L austenitic stainless steel in LWR and air environments
Chen, W., Spätig, P., & Seifert, H. P. (2021). Role of mean stress on fatigue behavior of a 316L austenitic stainless steel in LWR and air environments. International Journal of Fatigue, 145, 106111 (14 pp.). https://doi.org/10.1016/j.ijfatigue.2020.106111
Materials and corrosion issues in the primary coolant circuit of boiling water reactors
Seifert, H. P., & Bertsch, J. (2021). Materials and corrosion issues in the primary coolant circuit of boiling water reactors. Techniques de l'ingénieur, EBN 3 762 (30 pp.).
Dynamic study of contact damping in martensitic stainless steels using nano-indentation
Mouginot, R., Spätig, P., & Seifert, H. P. (2020). Dynamic study of contact damping in martensitic stainless steels using nano-indentation. Mechanics of Materials, 149, 103541 (10 pp.). https://doi.org/10.1016/j.mechmat.2020.103541
Microstructural characterization of the synergic effects of dynamic strain ageing and hydrogen on fracture behaviour of low-alloy RPV steels in high-temperature water environments
Que, Z., Heczko, M., Kuběna, I., Seifert, H. P., & Spätig, P. (2020). Microstructural characterization of the synergic effects of dynamic strain ageing and hydrogen on fracture behaviour of low-alloy RPV steels in high-temperature water environments. Materials Characterization, 165, 110405 (12 pp.). https://doi.org/10.1016/j.matchar.2020.110405
Corrosion and environmentally-assisted cracking of carbon and low-alloy steels
Seifert, H. P., Hickling, J., & Lister, D. (2020). Corrosion and environmentally-assisted cracking of carbon and low-alloy steels. In R. J. M. Konings & R. E. Stoller (Eds.), Vol. 4. Comprehensive nuclear materials (pp. 129-189). https://doi.org/10.1016/B978-0-12-803581-8.11763-1
Environmentally-assisted cracking of carbon and low-alloy steels in light water reactors
Seifert, H. P., & Ritter, S. (2020). Environmentally-assisted cracking of carbon and low-alloy steels in light water reactors. In S. Ritter (Ed.), European Federation of Corrosion publications: Vol. 69. Nuclear corrosion: research, progress and challenges (pp. 119-211). https://doi.org/10.1016/B978-0-12-823719-9.00005-6
Evaluation of quasi-static and dynamic fracture toughness on the low-alloy reactor pressure vessel steel JRQ in the transition region
Spätig, P., Mazánová, V., Suman, S., & Seifert, H. P. (2020). Evaluation of quasi-static and dynamic fracture toughness on the low-alloy reactor pressure vessel steel JRQ in the transition region. In S. A. Paipetis & F. M. H. Aliabadi (Eds.), Key engineering materials: Vol. 827. Advances in fracture and damage mechanics XVIII (pp. 294-299). https://doi.org/10.4028/www.scientific.net/KEM.827.294
Mean stress effect on fatigue behavior of austenitic stainless steel in air and LWR conditions
Chen, W., Spätig, P., & Seifert, H. P. (2019). Mean stress effect on fatigue behavior of austenitic stainless steel in air and LWR conditions. In J. A. F. O. Correia, A. M. P. De Jesus, A. A. Fernandes, & R. Calçada (Eds.), Structural integrity: Vol. 7. Mechanical fatigue of metals. Experimental and simulation perspectives. https://doi.org/10.1007/978-3-030-13980-3_8
Assessment of the SCC mitigation capabilities of the noble metal chemical application technology in a simulated BWR environment
Grundler, P. V., Ritter, S., Rowthu, S., & Seifert, H. P. (2019). Assessment of the SCC mitigation capabilities of the noble metal chemical application technology in a simulated BWR environment (pp. 189-198). Presented at the EnvDeg 2019. .
Degradation effects of hydrogen and high-temperature water environments on the fracture resistance of low-alloy RPV steels
Que, Z., Seifert, H. P., Spätig, P., Holzer, J., Zhang, A., Rao, G. S., & Ritter, S. (2019). Degradation effects of hydrogen and high-temperature water environments on the fracture resistance of low-alloy RPV steels (pp. 934-948). Presented at the EnvDeg 2019. .
Effect of dynamic strain ageing on environmental degradation of fracture resistance of low-alloy RPV steels in high-temperature water environments
Que, Z., Seifert, H. P., Spätig, P., Zhang, A., Holzer, J., Rao, G. S., & Ritter, S. (2019). Effect of dynamic strain ageing on environmental degradation of fracture resistance of low-alloy RPV steels in high-temperature water environments. Corrosion Science, 152, 172-189. https://doi.org/10.1016/j.corsci.2019.03.013
Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels
Que, Z., Seifert, H. P., Spätig, P., Rao, G. S., & Ritter, S. (2019). Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels. In J. H. Jackson, D. Paraventi, & M. Wright (Eds.), Minerals, metals & materials series. Proceedings of the 18th international conference on environmental degradation of materials in nuclear power systems - water reactors (pp. 1077-1099). https://doi.org/10.1007/978-3-319-67244-1_68
Environmental degradation of fracture resistance in high-temperature water environments of low-alloy reactor pressure vessel steels with high sulphur or phosphorus contents
Que, Z., Seifert, H. P., Spätig, P., Holzer, J., Zhang, A., Rao, G. S., & Ritter, S. (2019). Environmental degradation of fracture resistance in high-temperature water environments of low-alloy reactor pressure vessel steels with high sulphur or phosphorus contents. Corrosion Science, 154, 191-207. https://doi.org/10.1016/j.corsci.2019.04.011
Effect of temperature and surface treatment on SCC initiation in Alloy 182 weld metal under BWR conditions
Treichel, A., Ritter, S., Seifert, H. P., & Virtanen, S. (2019). Effect of temperature and surface treatment on SCC initiation in Alloy 182 weld metal under BWR conditions. Presented at the ICG-EAC annual meeting 2019. Tainan, Taiwan.
Effect of temperature and surface treatment on SCC initiation in alloy 182 weld metal under BWR conditions
Treichel, A., Ritter, S., Seifert, H. P., & Virtanen, S. (2019). Effect of temperature and surface treatment on SCC initiation in alloy 182 weld metal under BWR conditions. Presented at the EUROCORR 2019. Seville, Spain.
Electrochemical and spectroscopic characterization of oxide films formed on Alloy 182 in simulated boiling water reactor environment: effect of dissolved hydrogen
Bai, J., Bosch, R. W., Ritter, S., Schneider, C. W., Seifert, H. P., & Virtanen, S. (2018). Electrochemical and spectroscopic characterization of oxide films formed on Alloy 182 in simulated boiling water reactor environment: effect of dissolved hydrogen. Corrosion Science, 133, 204-216. https://doi.org/10.1016/j.corsci.2018.01.024
Stress corrosion cracking initiation and short crack growth behaviour in Alloy 182 weld metal under simulated boiling water reactor hydrogen water chemistry conditions
Bai, J., Ritter, S., Seifert, H. P., & Virtanen, S. (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. https://doi.org/10.1016/j.corsci.2017.11.021
The use of tapered specimens to evaluate the SCC initiation susceptibility in alloy 182 in BWR and PWR environments
Bai, J., Ritter, S., Seifert, H. P., Vankeerberghen, M., & Bosch, R. W. (2018). The use of tapered specimens to evaluate the SCC initiation susceptibility in alloy 182 in BWR and PWR environments. In J. H. Jackson, D. Paraventi, & M. Wright (Eds.), The minerals, metals & materials series. Proceedings of the 18th international conference on environmental degradation of materials in nuclear power systems – water reactors (pp. 1929-1948). https://doi.org/10.1007/978-3-030-04639-2_131
Fatigue behavior of 316L austenitic stainless steel in air and LWR environment with and without mean stress
Chen, W., Spätig, P., & Seifert, H. P. (2018). Fatigue behavior of 316L austenitic stainless steel in air and LWR environment with and without mean stress. In G. Henaff (Ed.), MATEC web of conferences: Vol. 165. 12th International Fatigue Congress (FATIGUE 2018) (p. 03012 (8 pp.). https://doi.org/10.1051/matecconf/201816503012
Evolution of the tensile properties of the tempered martensitic steel Eurofer97 after spallation irradiation at SINQ
Knitel, S., Spätig, P., Yamamoto, T., Seifert, H. P., Dai, Y., & Odette, G. R. (2018). Evolution of the tensile properties of the tempered martensitic steel Eurofer97 after spallation irradiation at SINQ. Nuclear Materials and Energy, 17, 69-77. https://doi.org/10.1016/j.nme.2018.09.002
 

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