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Crack propagation modeling in a PWR under PTS Using XFEM
Mora, D. F., Niffenegger, M., & Mukin, R. (2020). Crack propagation modeling in a PWR under PTS Using XFEM. In Pressure vessels and piping conference: Vol. 6. Materials and fabrication (p. V006T06A001). https://doi.org/10.1115/PVP2020-21026
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. Materials and fabrication: advanced and additive manufacturing and material technologies (pp. PVP2019-94019 (7 pp.). 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) (pp. 2536-2549). 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. Design and analysis: 4th international symposium on coke drum life cycle management (pp. PVP2019-94076 (10 pp.). 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) (pp. 2209-2222). 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
Effect of nuclear data on the DNBR prediction with subchannel code COBRA-TF
Mukin, R., Rochman, D., Clifford, I., Vasiliev, A., & Ferroukhi, H. (2018). Effect of nuclear data on the DNBR prediction with subchannel code COBRA-TF. In ANS international conference on best-estimate plus uncertainties methods (BEPU-2018) (p. 285 (6 pp.). American Nuclear Society.
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 (pp. ICONE26-81749 (7 pp.). 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 (pp. ICONE26-82546 (11 pp.). 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 (pp. ICONE26-81743 (13 pp.). 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 (p. (10 pp.). Presented at the 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2017). .
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 (p. (14 pp.). Presented at the 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2017). .
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 (p. N11A0310 (16 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). .
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
Simulation of flow on the secondary side of a steam generator bundle
Mukin, R., & Dehbi, A. (2016). Simulation of flow on the secondary side of a steam generator bundle. In Computational fluid dynamics for nuclear reactor safety-5. (CFD4NRS-5). Workshop proceedings.
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) (p. V004T10A018 (9 pp.). https://doi.org/10.1115/ICONE22-30517