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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
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 and hydrogen 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 and hydrogen on the fracture behaviour of low-alloy RPV steels. In J. H. Jackson, D. Paraventi, & M. Wright (Eds.), The minerals, metals & materials. Proceedings of the 18th international conference on environmental degradation of materials in nuclear power systems - water reactors. https://doi.org/10.1007/978-3-030-04639-2_68
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
Environmental degradation effect of high-temperature water and hydrogen on the fracture behavior of low-alloy reactor pressure vessel steels
Que, Z., Seifert, H. P., Spätig, P., Zhang, A., Rao, G. S., & Ritter, S. (2018). Environmental degradation effect of high-temperature water and hydrogen on the fracture behavior of low-alloy reactor pressure vessel steels. In A. Sedmak, Z. Radaković, & M. Rakin (Eds.), Procedia structural integrity: Vol. 13. ECF22 - loading and environmental effects on structural integrity (pp. 926-931). https://doi.org/10.1016/j.prostr.2018.12.174
Safe long-term operation in the context of environmental effects on fracture, fatigue and environmentally-assisted cracking. Final report of the SAFE-II project
Seifert, H. P., Ritter, S., Spätig, P., Bai, J., Chen, W., Rao, S. G., & Que, Z. (2018). Safe long-term operation in the context of environmental effects on fracture, fatigue and environmentally-assisted cracking. Final report of the SAFE-II project. (PSI Bericht, Report No.: 18-03). Paul Scherrer Institut.
Cyclic softening in annealed Zircaloy-2: role of edge dislocation dipoles and vacancies
Sudhakar Rao, G., Singh, S. R., Krsjak, V., & Singh, V. (2018). Cyclic softening in annealed Zircaloy-2: role of edge dislocation dipoles and vacancies. Journal of Nuclear Materials, 502, 154-160. https://doi.org/10.1016/j.jnucmat.2018.02.011
Rosette fracture of modified 9Cr-1Mo steel in tension
Verma, P., Sudhakar Rao, G., Santhi Srinivas, N. C., & Singh, V. (2017). Rosette fracture of modified 9Cr-1Mo steel in tension. Materials Science and Engineering A: Structural Materials: Properties, Microstructure and Processing, 683, 172-186. https://doi.org/10.1016/j.msea.2016.12.011
Ratcheting fatigue behavior of Zircaloy-2 at room temperature
Rajpurohit, R. S., Sudhakar Rao, G., Chattopadhyay, K., Santhi Srinivas, N. C., & Singh, V. (2016). Ratcheting fatigue behavior of Zircaloy-2 at room temperature. Journal of Nuclear Materials, 477, 67-76. https://doi.org/10.1016/j.jnucmat.2016.05.014
Corrosion and corrosion fatigue behavior of low nickel high nitrogen austenitic stainless steel
Rao, G. S., Singh, V., & Singhal, L. K. (2016). Corrosion and corrosion fatigue behavior of low nickel high nitrogen austenitic stainless steel (p. 17064 (9 pp.). Presented at the 17th asian pacific corrosion control conference (APCCC17). .
Effect of dynamic strain aging on cyclic stress response and deformation behavior of Zircaloy-2
Sudhakar Rao, G., Verma, P., Chakravartty, J. K., Nudurupati, S., Mahobia, G. S., Santhi Srinivas, N. C., & VakilSingh (2016). Effect of dynamic strain aging on cyclic stress response and deformation behavior of Zircaloy-2. In K. A. Venkata, C. Truman, & R. Wimpory (Eds.), Proceedings of the 7th international conference on creep, fatigue and creep-fatigue interaction (CF-7) (pp. 283-288). sine nomine.
Effect of hydrogen on tensile behavior of low alloy steel in the regime of dynamic strain ageing
Sudhakar Rao, G., Seifert, H. P., Ritter, S., Spätig, P., & Que, Z. (2016). Effect of hydrogen on tensile behavior of low alloy steel in the regime of dynamic strain ageing. In F. Iacoviello, L. Susmel, D. Firrao, & G. Ferro (Eds.), Procedia structural integrity: Vol. 2. 21st European conference on fracture, ECF21, 20-24 June 2016, Catania, Italy (pp. 3399-3406). https://doi.org/10.1016/j.prostr.2016.06.424