| 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 |
| 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 |
| 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 |
| 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. |
| 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 |
| Application of CTF subchannel code for BWR reload licensing analysis support
Nikitin, K., Arnold, B., Clifford, I., & Ferroukhi, H. (2023). Application of CTF subchannel code for BWR reload licensing analysis support. In 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 5569-5578). https://doi.org/10.13182/NURETH20-40978 |
| Parametric study on the modeling of the open passive containment cooling system (CWC)
Al-Yahia, O. S., Clifford, I., Nikitin, K., & Ferroukhi, H. (2022). Parametric study on the modeling of the open passive containment cooling system (CWC) (p. N13P113 (9 pp.). Presented at the The 13th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-13). . |
| 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 |