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Effect of material inhomogeneity on constraint loss measured with subsized C(T) fracture specimens of a reactor pressure vessel steel
Jiang, D., Spätig, P., & Seifert, H. P. (2024). Effect of material inhomogeneity on constraint loss measured with subsized C(T) fracture specimens of a reactor pressure vessel steel. Journal of Nuclear Materials, 588, 154801 (9 pp.). https://doi.org/10.1016/j.jnucmat.2023.154801
On the determination of the reference temperature T<sub>0</sub> of the Master-Curve method using subsized compact tension specimens
Zhou, D., Jiang, D., Spätig, P., & Seifert, H. P. (2024). On the determination of the reference temperature T0 of the Master-Curve method using subsized compact tension specimens. In F. Aliabadi & Z. S. Khodaei (Eds.), Procedia structural integrity: Vol. 52. International conference on fracture, damage and structural health monitoring (pp. 430-437). https://doi.org/10.1016/j.prostr.2023.12.044
Assessment of gage length effects on cylindrical austenitic stainless steel fatigue specimens in air and high-temperature water environment
Baykal, B. A., Spätig, P., & Seifert, H. P. (2023). Assessment of gage length effects on cylindrical austenitic stainless steel fatigue specimens in air and high-temperature water environment. In ASME pressure vessels and piping conference: Vol. 5. Materials & Fabrication (p. 105910 (9 pp.). https://doi.org/10.1115/PVP2023-105910
Effect of zinc injection on mitigating stress corrosion cracking initiation of structural materials in light water reactor primary water
Chen, K., Mackiewicz, A., Virtanen, S., Grundler, P. V., Seifert, H. P., & Ritter, S. (2023). Effect of zinc injection on mitigating stress corrosion cracking initiation of structural materials in light water reactor primary water. Corrosion Reviews, 41(3), 387-398. https://doi.org/10.1515/corrrev-2022-0098
Role of Zn injection on mitigating stress corrosion cracking initiation of Alloy 182 weld metal in simulated light water reactor environment
Chen, K., Mackiewicz, A., Seifert, H. P., Virtanen, S., & Ritter, S. (2023). Role of Zn injection on mitigating stress corrosion cracking initiation of Alloy 182 weld metal in simulated light water reactor environment. Corrosion Science, 221, 111364 (13 pp.). https://doi.org/10.1016/j.corsci.2023.111364
Assessing the role of surface conditions in SCC susceptibility of Alloy 182 in simulated LWR environments
Das, A., Seifert, H. P., & Ritter, S. (2023). Assessing the role of surface conditions in SCC susceptibility of Alloy 182 in simulated LWR environments. Presented at the EUROCORR 2023. Brussels.
Effect of zinc water chemistry on the corrosion and stress corrosion cracking behavior of structural materials in light water reactors - a review
Guo, X., Chen, K., Seifert, H. P., & Ritter, S. (2023). Effect of zinc water chemistry on the corrosion and stress corrosion cracking behavior of structural materials in light water reactors - a review. PPCHEM, 25(3), 124-147.
Effect of Zinc on the oxide film properties of Alloy 182 exposed to BWR environment
Mackiewicz, A., Ritter, S., Chen, K., Seifert, H. P., & Virtanen, S. (2023). Effect of Zinc on the oxide film properties of Alloy 182 exposed to BWR environment. Presented at the Annual meeting of the international cooperative group on environmentally-assisted cracking of water reactor materials (ICG-EAC meeting). Kingston: ICG-EAC.
Effect of zinc water chemistry on stress corrosion cracking mitigation of alloy 182 weld metal and its oxide film properties
Mackiewicz, A., Ritter, S., Chen, K., Seifert, H. P., & Virtanen, S. (2023). Effect of zinc water chemistry on stress corrosion cracking mitigation of alloy 182 weld metal and its oxide film properties. In International conference on water chemistry in nuclear reactor systems (NPC 2023) (p. (10 pp.). Sfen.
Effect of surface machining on the environmentally-assisted cracking of Alloy 182 and 316L stainless steel in light water reactor environments: results of the collaborative project MEACTOS
Zimina, M., Ritter, S., Zajec, B., Vankeerberghen, M., Volpe, L., Hojná, A., … Seifert, H. P. (2023). Effect of surface machining on the environmentally-assisted cracking of Alloy 182 and 316L stainless steel in light water reactor environments: results of the collaborative project MEACTOS. Corrosion Reviews, 41(5), 545-564. https://doi.org/10.1515/corrrev-2022-0121
Hydrogen embrittlement on fracture resistance of low-alloy reactor pressure vessel steel with high dynamic strain aging at 288 °C
Que, Z., Seifert, H. P., Mazánová, V., & Spätig, P. (2022). Hydrogen embrittlement on fracture resistance of low-alloy reactor pressure vessel steel with high dynamic strain aging at 288 °C. Materials Letters, 308, 131269 (5 pp.). https://doi.org/10.1016/j.matlet.2021.131269
Impact of chloride on the environmentally-assisted crack initiation behaviour of low-alloy steel under boiling water reactor conditions
Ritter, S., & Seifert, H. P. (2022). Impact of chloride on the environmentally-assisted crack initiation behaviour of low-alloy steel under boiling water reactor conditions. Corrosion and Materials Degradation, 3(2), 178-191. https://doi.org/10.3390/cmd3020010
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
Zinc injection in light water reactors to mitigate stress corrosion cracking of Alloy 182 and 316L stainless steel
Mackiewicz, A., Ritter, S., Chen, K., Seifert, H. P., & Virtanen, S. (2021). Zinc injection in light water reactors to mitigate stress corrosion cracking of Alloy 182 and 316L stainless steel. Presented at the Annual meeting of the international cooperative group on environmentally-assisted cracking of water reactor materials. Mills River, USA: ICG-EAC.
Zinc injection in light water reactors to mitigate stress corrosion cracking of alloy 182 and cold-worked type 316L stainless steel
Mackiewicz, A., Ritter, S., Chen, K., Seifert, H. P., & Virtanen, S. (2021). Zinc injection in light water reactors to mitigate stress corrosion cracking of alloy 182 and cold-worked type 316L stainless steel. Presented at the EUROCORR 2021. The European corrosion congress. Budapest.
Study on hydrogen embrittlement and dynamic strain ageing on low-alloy reactor pressure vessel steels
Rao, G. S., Yagodzinskyy, Y., Que, Z., Spätig, P., & Seifert, H. P. (2021). Study on hydrogen embrittlement and dynamic strain ageing on low-alloy reactor pressure vessel steels. Journal of Nuclear Materials, 556, 153161 (13 pp.). https://doi.org/10.1016/j.jnucmat.2021.153161
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
 

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