| Synthesis of a CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction
Andreani, M., Gaikwad, A. J., Ganju, S., Gera, B., Grigoryev, S., Herranz, L. E., … Zhang, R. (2019). Synthesis of a CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction. Nuclear Engineering and Design, 354, 110177 (31 pp.). https://doi.org/10.1016/j.nucengdes.2019.110177 |
| 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 |
| Effect of non-uniform reactor cooling on fracture and constraint of a reactor pressure vessel
Qian, G., Niffenegger, M., Sharabi, M., & Lafferty, N. (2018). Effect of non-uniform reactor cooling on fracture and constraint of a reactor pressure vessel. Fatigue and Fracture of Engineering Materials and Structures, 41(7), 1559-1575. https://doi.org/10.1111/ffe.12796 |
| Synthesis of a blind CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction
Andreani, M., Daqiang, Y., Gaikwad, A. J., Ganju, S., Gera, B., Grigoryev, S., … Paladino, D. (2016). Synthesis of a blind CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction. In Computational fluid dynamics for nuclear reactor safety applications-6 (CFD4NRS-6). Workshop proceedings (p. (13 pp.). OECD; NEA. |
| Coupled RELAP5, 3D CFD and FEM analysis of postulated cracks in RPVs subjected to PTS loading
González-Albuixech, V. F., Qian, G., Sharabi, M., Niffenegger, M., Niceno, B., & Lafferty, N. (2016). Coupled RELAP5, 3D CFD and FEM analysis of postulated cracks in RPVs subjected to PTS loading. Nuclear Engineering and Design, 297, 111-122. https://doi.org/10.1016/j.nucengdes.2015.11.032 |
| Integrity analysis of a reactor pressure vessel subjected to a realistic pressurized thermal shock considering the cooling plume and constraint effects
González-Albuixech, V. F., Qian, G., Sharabi, M., Niffenegger, M., Niceno, B., & Lafferty, N. (2016). Integrity analysis of a reactor pressure vessel subjected to a realistic pressurized thermal shock considering the cooling plume and constraint effects. Engineering Fracture Mechanics, 162, 201-217. https://doi.org/10.1016/j.engfracmech.2016.05.010 |
| Computational study of platinum nanoparticle deposition on the surfaces of crevices
Gu, H. F., Niceno, B., Grundler, P. V., Sharabi, M., Veleva, L., & Ritter, S. (2016). Computational study of platinum nanoparticle deposition on the surfaces of crevices. Nuclear Engineering and Design, 304, 84-99. https://doi.org/10.1016/j.nucengdes.2016.04.020 |
| Outcomes from the EURATOM–ROSATOM ERCOSAM SAMARA projects on containment thermal-hydraulics for severe accident management
Paladino, D., Andreani, M., Guentay, S., Mignot, G., Kapulla, R., Paranjape, S., … Visser, D. (2016). Outcomes from the EURATOM–ROSATOM ERCOSAM SAMARA projects on containment thermal-hydraulics for severe accident management. Nuclear Engineering and Design, 308, 103-114. https://doi.org/10.1016/j.nucengdes.2016.08.011 |
| Deterministic and probabilistic PTS study for a reactor pressure vessel considering plume cooling effects
Qian, G., Niffenegger, M., Sharabi, M., & Lafferty, N. (2016). Deterministic and probabilistic PTS study for a reactor pressure vessel considering plume cooling effects. In Conference proceedings. Pressure vessels and piping conference: Vol. 6A-2016. Materials and fabrication (pp. PVP2016-63869 (12 pp.). https://doi.org/10.1115/PVP2016-63869 |
| Probabilistic pressurized thermal shock analysis for a reactor pressure vessel considering plume cooling effect
Qian, G., González-Albuixech, V. F., Niffenegger, M., & Sharabi, M. (2016). Probabilistic pressurized thermal shock analysis for a reactor pressure vessel considering plume cooling effect. Journal of Pressure Vessel Technology, 138(4), 041204 (8 pp.). https://doi.org/10.1115/1.4032197 |
| Computational fluid dynamics study of pressurized thermal shock phenomena in the reactor pressure vessel
Sharabi, M., González-Albuixech, V. F., Lafferty, N., Niceno, B., & Niffenegger, M. (2016). Computational fluid dynamics study of pressurized thermal shock phenomena in the reactor pressure vessel. Nuclear Engineering and Design, 299, 136-145. https://doi.org/10.1016/j.nucengdes.2015.10.014 |
| Comparison of PTS analyses of RPVs based on 3D-CFD and RELAP5
González-Albuixech, V. F., Qian, G., Sharabi, M., Niffenegger, M., Niceno, B., & Lafferty, N. (2015). Comparison of PTS analyses of RPVs based on 3D-CFD and RELAP5. Nuclear Engineering and Design, 291, 168-178. https://doi.org/10.1016/j.nucengdes.2015.05.025 |
| Turbulent gas mixing in strong density stratified shear and non-shear flows
Krohn, B., Sharabi, M., Nicenou, B., Prasser, H. M., Bijleveld, H., Shams, A., & Roelofs, F. (2015). Turbulent gas mixing in strong density stratified shear and non-shear flows. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015: Vol. 6. 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16) (pp. 4436-4449). American Nuclear Society. |
| Results of 4-equation turbulence models in the prediction of heat transfer to supercritical pressure fluids
Pucciarelli, A., Borroni, I., Sharabi, M., & Ambrosini, W. (2015). Results of 4-equation turbulence models in the prediction of heat transfer to supercritical pressure fluids. Nuclear Engineering and Design, 281, 5-14. https://doi.org/10.1016/j.nucengdes.2014.11.004 |
| Probabilistic pressurized thermal shocks analysis for a reactor pressure vessel by considering plume effect
Qian, G., González-Albuixech, V. F., Niffenegger, M., & Sharabi, M. (2015). Probabilistic pressurized thermal shocks analysis for a reactor pressure vessel by considering plume effect. In Pressure vessels and piping conference: Vol. 6A. Proceedings of the ASME 2015 pressure vessels and piping conference. Materials and fabrication (pp. PVP2015-45963 (9 PP.). https://doi.org/10.1115/PVP2015-45963 |
| Computational analyses of the thermal stress induced by coolant mixing in a T-joint
Janssens, K. G. F., Niffenegger, M., & Sharabi, M. (2014). Computational analyses of the thermal stress induced by coolant mixing in a T-joint. In Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22) (p. V001T02A005 (9 pp.). https://doi.org/10.1115/ICONE22-30218 |
| Crack initiation in austenitic stainless steel due to cyclic thermal shocks and biaxial preload
Niffenegger, M., Niceno, B., Sharabi, M., Janssens, K. G. F., & Reichlin, K. (2014). Crack initiation in austenitic stainless steel due to cyclic thermal shocks and biaxial preload. In 22nd conference on structural mechanics in reactor technology (p. (10 pp.). Curran. |
| Large eddy simulation of turbulent heat transfer at supercritical pressures
Ničeno, B., & Sharabi, M. (2013). Large eddy simulation of turbulent heat transfer at supercritical pressures. Nuclear Engineering and Design, 261, 44-55. https://doi.org/10.1016/j.nucengdes.2013.03.042 |
| Capabilities of two-equation low-Reynolds number turbulence models in predicting heat transfer to fluids at supercritical pressure
Sharabi, M. (2013). Capabilities of two-equation low-Reynolds number turbulence models in predicting heat transfer to fluids at supercritical pressure. Presented at the 15th international topical meeting on nuclear reactor thermal-hydraulics, NURETH-15. Pisa, Italy. |
| Analysis of the ISP-50 Direct Vessel Injection SBLOCA in the ATLAS facility with the RELAP5/MOD3.3 code
Sharabi, M., & Freixa, J. (2012). Analysis of the ISP-50 Direct Vessel Injection SBLOCA in the ATLAS facility with the RELAP5/MOD3.3 code. Nuclear Engineering and Technology, 44(7), 709-718. https://doi.org/10.5516/NET.02.2012.712 |
