| OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment
Martinez-Quiroga, V., Szogradi, M., Schollenberger, S., Sanchez-Perea, M., Sandberg, N., Zhongyun, J., … Freixa, J. (2022). OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment. Nuclear Engineering and Design, 389, 111632 (20 pp.). https://doi.org/10.1016/j.nucengdes.2021.111632 |
| 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 |
| Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach
Mora, D. F., Costa Garrido, O., Mukin, R., & Niffenegger, M. (2020). Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach. Engineering Fracture Mechanics, 238, 107258 (16 pp.). https://doi.org/10.1016/j.engfracmech.2020.107258 |
| 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. |
| 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 (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). . |
| 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 (p. N11A0310 (16 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). . |
