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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
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
Modeling noise experiments performed at AKR-2 and CROCUS zero-power reactors
Hursin, M., Zoia, A., Rouchon, A., Brighenti, A., Zmijarevic, I., Santandrea, S., … Verdú, G. (2023). Modeling noise experiments performed at AKR-2 and CROCUS zero-power reactors. Annals of Nuclear Energy, 194, 110066 (16 pp.). https://doi.org/10.1016/j.anucene.2023.110066
 

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