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Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs
Clifford, I., Pecchia, M., Mukin, R., Cozzo, C., Ferroukhi, H., & Gorzel, A. (2019). Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs. Annals of Nuclear Energy, 130, 440-451. https://doi.org/10.1016/j.anucene.2019.03.017
Fracture mechanics analysis of a PWR under PTS using XFEM and input from TRACE
Mora, D. F., Mukin, R., Costa Garrido, O., & Niffenegger, M. (2019). Fracture mechanics analysis of a PWR under PTS using XFEM and input from TRACE. In PVP - American Society of Mechanical Engineers. Pressure vessels and piping division: Vol. 6A. ASME 2019 pressure vessels & piping conference. Conference proceedings. Materials and fabrication. https://doi.org/10.1115/PVP2019-94019
Screening analysis for pressurized thermal shock (PTS) transient scenarios
Mukin, R., Clifford, I., Costa Garrido, O., Mora, D. F., Niffenegger, M., Niceno, B., & Ferroukhi, H. (2019). Screening analysis for pressurized thermal shock (PTS) transient scenarios. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, USA: American Nuclear Society (ANS).
Uncertainties in pressurized thermal shock analyses
Niffenegger, M., Garrido, O. C., Mora, D. F., Qian, G., Mukin, R., Sharabi, M., … Niceno, B. (2019). Uncertainties in pressurized thermal shock analyses. In PVP - American Society of Mechanical Engineers. Pressure vessels and piping division: Vol. 3. ASME 2019 pressure vessels & piping conference. Conference proceedings. Design and analysis. https://doi.org/10.1115/PVP2019-94076
Comparison of computational fluid dynamics and subchannel numerical solutions of fuel assemblies characterized by bowing
Puragliesi, R., Mukin, R., Clifford, I., Ferroukhi, H., & Seidl, M. (2019). Comparison of computational fluid dynamics and subchannel numerical solutions of fuel assemblies characterized by bowing. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS).
Unsteady single-phase natural-circulation flow mixing prediction using 3-D thermal-hydraulic system and CFD Codes
Bousbia Salah, A., Ceuca, S. C., Puragliesi, R., Mukin, R., Grahn, A., Kliem, S., … Austregesilo, H. (2018). Unsteady single-phase natural-circulation flow mixing prediction using 3-D thermal-hydraulic system and CFD Codes. Nuclear Technology, 203(3), 293-314. https://doi.org/10.1080/00295450.2018.1461517
Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE
Mukin, R., Clifford, I., Zerkak, O., & Ferroukhi, H. (2018). Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE. Nuclear Engineering and Technology, 50(3), 356-367. https://doi.org/10.1016/j.net.2017.12.005
Pressurized Thermal Shock (PTS) transient scenarios analysis with TRACE
Mukin, R., Clifford, I., Ferroukhi, H., & Niffenegger, M. (2018). Pressurized Thermal Shock (PTS) transient scenarios analysis with TRACE. In Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. https://doi.org/10.1115/ICONE26-81749
Sensitivity of CTF solution to subchannel window size
Mukin, R., Seidl, M., Clifford, I., & Ferroukhi, H. (2018). Sensitivity of CTF solution to subchannel window size. In Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. https://doi.org/10.1115/ICONE26-82546
Subchannel modeling of single rod bowing in a bundle geometry
Mukin, R., Puragliesi, R., Pecchia, M., & Seidl, M. (2018). Subchannel modeling of single rod bowing in a bundle geometry. Nuclear Engineering and Design, 340, 347-369. https://doi.org/10.1016/j.nucengdes.2018.09.032
Computational fluid dynamics as a tool for deriving subchannel model parameters - The PSBT case study
Puragliesi, R., Mukin, R., Clifford, I., Ferroukhi, H., & Seidl, M. (2018). Computational fluid dynamics as a tool for deriving subchannel model parameters - The PSBT case study. In Vol. 8. Proceedings of the 26th international conference on nuclear engineering (ICONE26). Computational fluid dynamics (CFD); nuclear education and public acceptance. https://doi.org/10.1115/ICONE26-81743
Thermal hydraulic analysis of PWR assembly bowing using subchannel code COBRA-TF
Mukin, R., Clifford, I., Ferroukhi, H., & Seidl, M. (2017). Thermal hydraulic analysis of PWR assembly bowing using subchannel code COBRA-TF. Presented at the 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2017). Xi'an, China.
Thermal mixing assessment using 3-D thermal-hydraulic and CFD codes
Mukin, R., Puragliesi, R., Ceuca, S. C., Austregesilo, H., & Bousbia Salah, A. (2017). Thermal mixing assessment using 3-D thermal-hydraulic and CFD codes. Presented at the 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2017). Xi'an, China.
Key findings from the artist project on aerosol retention in a dry steam generator
Dehbi, A., Suckow, D., Lind, T., Guentay, S., Danner, S., & Mukin, R. (2016). Key findings from the artist project on aerosol retention in a dry steam generator. Nuclear Engineering and Technology, 48(4), 870-880. https://doi.org/10.1016/j.net.2016.06.001
Bubble reconstruction method for wire-mesh sensors measurements
Mukin, R. V. (2016). Bubble reconstruction method for wire-mesh sensors measurements. Experiments in Fluids, 57(8), 133 (12 pp.). https://doi.org/10.1007/s00348-016-2220-y
Modeling and analysis of selected OECD PKL3 Station-Blackout experiments using TRACE
Mukin, R., Zerkak, O., & Pautz, A. (2016). Modeling and analysis of selected OECD PKL3 Station-Blackout experiments using TRACE. Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). Gyeongju, Korea.
Particle deposition modeling in the secondary side of a steam generator bundle model
Mukin, R., & Dehbi, A. (2016). Particle deposition modeling in the secondary side of a steam generator bundle model. Nuclear Engineering and Design, 299, 112-123. https://doi.org/10.1016/j.nucengdes.2015.09.001
Modeling of bubble coalescence and break-up in turbulent bubbly flow
Mukin, R. V. (2014). Modeling of bubble coalescence and break-up in turbulent bubbly flow. International Journal of Multiphase Flow, 62, 52-66. https://doi.org/10.1016/j.ijmultiphaseflow.2014.02.008
Simulation of a gas jet in the secondary side of a steam generator bundle following a tube rupture sequence
Mukin, R., & Dehbi, A. (2014). Simulation of a gas jet in the secondary side of a steam generator bundle following a tube rupture sequence. In Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). https://doi.org/10.1115/ICONE22-30517
Simulation of flow in the secondary side of a steam generator bundle
Mukin, R. V., & Dehbi, A. (2014). Simulation of flow in the secondary side of a steam generator bundle. In Vol. 1. Proceedings of the OECD/NEA & IAEA workshop on computational fluid dynamics for nuclear safety research, ETH Zuerich. Switzerland.