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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
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
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
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
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
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
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 of hydrogen behavior in liner claddings
Konarski, P., Cozzo, C., Khvostov, G., & Ferroukhi, H. (2023). Modeling of hydrogen behavior in liner claddings. Journal of Nuclear Materials, 573, 154125 (11 pp.). https://doi.org/10.1016/j.jnucmat.2022.154125
Addressing practical aspects of the nuclear criticality safety evaluations with frequentist statistics
Lee, H., Vasiliev, A., & Ferroukhi, H. (2023). Addressing practical aspects of the nuclear criticality safety evaluations with frequentist statistics. Annals of Nuclear Energy, 181, 109556 (17 pp.). https://doi.org/10.1016/j.anucene.2022.109556
Iterative Bayesian Monte Carlo for nuclear data evaluation
Alhassan, E., Rochman, D., Vasiliev, A., Hursin, M., Koning, A. J., & Ferroukhi, H. (2022). Iterative Bayesian Monte Carlo for nuclear data evaluation. Nuclear Science and Techniques, 33(4), 50 (31 pp.). https://doi.org/10.1007/s41365-022-01034-w
Appraisal of the NRC H-uptake calculation for Swiss boiling water reactors
Cozzo, C., Khvostov, G., Clifford, I., & Ferroukhi, H. (2022). Appraisal of the NRC H-uptake calculation for Swiss boiling water reactors. Nuclear Engineering and Design, 391, 111731 (5 pp.). https://doi.org/10.1016/j.nucengdes.2022.111731
A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments
Dokhane, A., Vasiliev, A., Hursin, M., Rochman, D., & Ferroukhi, H. (2022). A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments. Nuclear Engineering and Technology, 54(5), 1804-1812. https://doi.org/10.1016/j.net.2021.10.042
On butterfly effect in the dynamics of Oskarshamn-2 instability event of 1999
Dokhane, A., Vasiliev, A., & Ferroukhi, H. (2022). On butterfly effect in the dynamics of Oskarshamn-2 instability event of 1999. Nuclear Engineering and Design, 399, 112016 (12 pp.). https://doi.org/10.1016/j.nucengdes.2022.112016
Analysis of Rostov-II benchmark using conventional two-step code systems
Jang, J., Hursin, M., Lee, W., Pautz, A., Papadionysiou, M., Ferroukhi, H., & Lee, D. (2022). Analysis of Rostov-II benchmark using conventional two-step code systems. Energies, 15(9), 3318 (24 pp.). https://doi.org/10.3390/en15093318
Methodology for CPR estimations of BWR cycle specific transient reload analyses using CTF sub-channel code
Nikitin, K., Clifford, I., Dokhane, A., & Ferroukhi, H. (2022). Methodology for CPR estimations of BWR cycle specific transient reload analyses using CTF sub-channel code. Nuclear Engineering and Design, 389, 111649 (14 pp.). https://doi.org/10.1016/j.nucengdes.2022.111649
 

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