| Assessment of TRACE code for modeling of passive safety system during long transient SBO via PKL/SACO facility
Al-Yahia, O. S., Clifford, I., & Ferroukhi, H. (2024). Assessment of TRACE code for modeling of passive safety system during long transient SBO via PKL/SACO facility. Nuclear Engineering and Technology. https://doi.org/10.1016/j.net.2024.02.050 |
| The influence of droplet breakup model on the prediction of reactor core parameters during reflood conditions
Al-Yahia, O. S., Bernard, M., Clifford, I., Perret, G., Bajorek, S., & Ferroukhi, H. (2024). The influence of droplet breakup model on the prediction of reactor core parameters during reflood conditions. Nuclear Engineering and Design, 416, 112815 (16 pp.). https://doi.org/10.1016/j.nucengdes.2023.112815 |
| Monte Carlo analysis of BWR geometries using a cycle check-up methodology
Hursin, M., Vasiliev, A., Rochman, D., Dokhane, A., & Ferroukhi, H. (2024). Monte Carlo analysis of BWR geometries using a cycle check-up methodology. Annals of Nuclear Energy, 195, 110170 (17 pp.). https://doi.org/10.1016/j.anucene.2023.110170 |
| Development and testing of the hydrogen behavior tool for Falcon - HYPE
Konarski, P., Cozzo, C., Khvostov, G., & Ferroukhi, H. (2024). Development and testing of the hydrogen behavior tool for Falcon - HYPE. Nuclear Engineering and Technology, 56(2), 728-744. https://doi.org/10.1016/j.net.2023.11.012 |
| Minimal requirements to thermal-hydraulics/3D-neutron kinetics clustering for BWR transient analysis
Nikitin, K., Clifford, I., & Ferroukhi, H. (2024). Minimal requirements to thermal-hydraulics/3D-neutron kinetics clustering for BWR transient analysis. Annals of Nuclear Energy, 195, 110147 (12 pp.). https://doi.org/10.1016/j.anucene.2023.110147 |
| Two-phase hydrodynamics and aerosol mass transfer characterization in pool scrubbing: a simultaneous measurement technique
Ramos Perez, A., Lind, T., Petrov, V., Manera, A., & Prasser, H. M. (2024). Two-phase hydrodynamics and aerosol mass transfer characterization in pool scrubbing: a simultaneous measurement technique. Journal of Aerosol Science, 178, 106336 (17 pp.). https://doi.org/10.1016/j.jaerosci.2024.106336 |
| High-resolution cross section measurements for neutron interactions on <sup>89</sup>Y with incident neutron energies up to 95 keV
Tagliente, G., Milazzo, P. M., Paradela, C., Kopecky, S., Vescovi, D., Alaerts, G., … Žugec, P. (2024). High-resolution cross section measurements for neutron interactions on 89Y with incident neutron energies up to 95 keV. European Physical Journal A: Hadrons and Nuclei, 60(1), 21 (18 pp.). https://doi.org/10.1140/epja/s10050-024-01243-4 |
| Experimental study for high Reynolds’ gas-liquid two-phase flow through rod bundle using Wire Mesh Sensor (WMS)
Al-Yahia, O. S., Clifford, I., Bissels, W. M., Suckow, D., & Ferroukhi, H. (2023). Experimental study for high Reynolds’ gas-liquid two-phase flow through rod bundle using Wire Mesh Sensor (WMS). Nuclear Engineering and Design, 405, 112224 (23 pp.). https://doi.org/10.1016/j.nucengdes.2023.112224 |
| Implementation of a three-field framework in TRACE to improve the prediction of reactor core reflood conditions part II
Al-Yahia, O. S., Bernard, M., Clifford, I., Perret, G., Bajorek, S., & Ferroukhi, H. (2023). Implementation of a three-field framework in TRACE to improve the prediction of reactor core reflood conditions part II. In 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 110-122). https://doi.org/10.13182/NURETH20-40133 |
| TRACE code simulation of the interaction between reactor coolant system and containment building with passive heat removal system
Al-Yahia, O. S., Clifford, I., Nikitin, K., Liu, P., & Ferroukhi, H. (2023). TRACE code simulation of the interaction between reactor coolant system and containment building with passive heat removal system. Nuclear Engineering and Design, 406, 112234 (21 pp.). https://doi.org/10.1016/j.nucengdes.2023.112234 |
| Results of the <sup>244</sup>Cm, <sup>246</sup>Cm and <sup>248</sup>Cm neutron-induced capture cross sections measurements at EAR1 and EAR2 of the n_TOF facility
Alcayne, V., Mendoza, E., Cano-Ott, D., Kimura, A., Aberle, O., Amaducci, S., … Žugec, P. (2023). Results of the 244Cm, 246Cm and 248Cm neutron-induced capture cross sections measurements at EAR1 and EAR2 of the n_TOF facility. In C. M. Mattoon, R. Vogt, J. Escher, & I. Thompson (Eds.), EPJ web conferences: Vol. 284. 15th international conference on nuclear data for science and technology (ND2022) (p. 01009 (6 pp.). https://doi.org/10.1051/epjconf/202328401009 |
| TENDL-based evaluation and adjustment of p+<sup>111</sup>Cd between 1 and 100 MeV
Alhassan, E., Rochman, D., Vasiliev, A., Koning, A. J., & Ferroukhi, H. (2023). TENDL-based evaluation and adjustment of p+111Cd between 1 and 100 MeV. Applied Radiation and Isotopes, 198, 110832 (15 pp.). https://doi.org/10.1016/j.apradiso.2023.110832 |
| High resolution <sup>80</sup>Se(n,<em>γ</em>) cross section measurement at CERN n_TOF
Babiano-Suarez, V., Balibrea-Correa, J., Caballero-Ontanaya, L., Domingo-Pardo, C., Ladarescu, I., Lerendegui-Marco, J., … Žugec, P. (2023). High resolution 80Se(n,γ) cross section measurement at CERN n_TOF. In C. M. Mattoon, R. Vogt, J. Escher, & I. Thompson (Eds.), EPJ web conferences: Vol. 284. 15th international conference on nuclear data for science and technology (ND2022) (p. 01001 (6 pp.). https://doi.org/10.1051/epjconf/202328401001 |
| Acceleration of nuclear reactor simulation and uncertainty quantification using low-precision arithmetic
Cherezov, A., Vasiliev, A., & Ferroukhi, H. (2023). Acceleration of nuclear reactor simulation and uncertainty quantification using low-precision arithmetic. Applied Sciences, 13(2), 896 (14 pp.). https://doi.org/10.3390/app13020896 |
| TRACE investigation on the performance of passive safety condenser as ultimate heat sink
Clifford, I., Al-Yahia, O. S., & Ferroukhi, H. (2023). TRACE investigation on the performance of passive safety condenser as ultimate heat sink. In Proceedings of Saudi international conference on nuclear power engineering (SCOPE) (p. 23220 (6 pp.). SCOPE. |
| Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: first outcomes
Coindreau, O., Herranz, L. E., Bocanegra, R., Ederli, S., Maccari, P., Mascari, F., … Nudi, M. (2023). Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: first outcomes. Annals of Nuclear Energy, 188, 109796 (9 pp.). https://doi.org/10.1016/j.anucene.2023.109796 |
| Nuclear data effect on BWR stability parameter uncertainty at stable core conditions
Dokhane, A., Vasiliev, A., Hursin, M., & Ferroukhi, H. (2023). Nuclear data effect on BWR stability parameter uncertainty at stable core conditions. Nuclear Engineering and Design, 414, 112620 (9 pp.). https://doi.org/10.1016/j.nucengdes.2023.112620 |
| Methyl iodide retention in Ag-Zeolite material under filtered containment venting system condition
Espegren, F., Suckow, D., Lind, T., Mantzaras, J., & Theile, J. (2023). Methyl iodide retention in Ag-Zeolite material under filtered containment venting system condition. In 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 3759-3771). https://doi.org/10.13182/NURETH20-40735 |
| Assessment of the influence of scaling on turbulent mixing in downcomer and core-inlet flow distribution
Fogliatto, E., Puragliesi, R., Clifford, I., & Ferroukhi, H. (2023). Assessment of the influence of scaling on turbulent mixing in downcomer and core-inlet flow distribution. Annals of Nuclear Energy, 185, 109715 (15 pp.). https://doi.org/10.1016/j.anucene.2023.109715 |
| Criticality assessments for long-term post-closure canister corrosion scenarios in a deep geological repository
Frankl, M., Wittel, M., Diomidis, N., Vasiliev, A., Ferroukhi, H., & Pudollek, S. (2023). Criticality assessments for long-term post-closure canister corrosion scenarios in a deep geological repository. Annals of Nuclear Energy, 180, 109449 (9 pp.). https://doi.org/10.1016/j.anucene.2022.109449 |