| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| The influence of scaling on turbulent mixing in reactor pressure vessels and core-inlet flow distribution
Fogliatto, E., Clifford, I., Ferroukhi, H., & Puragliesi, R. (2022). The influence of scaling on turbulent mixing in reactor pressure vessels and core-inlet flow distribution. In 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19) (p. 35578 (14 pp.). American Nuclear Society. |
| Comparison of CASMO-5, MPACT and Serpent 2 for the modeling of advanced BWR lattices
Hursin, M., Mala, P., Vasiliev, A., Ferroukhi, H., Liu, Y., Choi, S., & Kochunas, B. (2022). Comparison of CASMO-5, MPACT and Serpent 2 for the modeling of advanced BWR lattices. In International conference on physics of reactors 2022 (PHYSOR 2022) (pp. 2762-2772). American Nuclear Society. |
| 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 |
| Verification of legacy methodology of minimum critical mass estimation at PSI
Lee, H., Vasiliev, A., & Ferroukhi, H. (2022). Verification of legacy methodology of minimum critical mass estimation at PSI (p. (8 pp.). Presented at the GLOBAL 2022 - sustainable energy beyond the pandemic. . |
| CPR estimation by CTF subchannel code with machine learning support
Nikitin, K., Arnold, B., Clifford, I., & Ferroukhi, H. (2022). CPR estimation by CTF subchannel code with machine learning support (p. N13P156 (10 pp.). Presented at the The 13th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-13). . |
| 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 |
| Coupling of COBRA-TF to nTRACER for full core high fidelity analysis of VVERs
Papadionysiou, M., Seongchan, K., Hursin, M., Vasiliev, A., Ferroukhi, H., Pautz, A., & Joo, H. G. (2022). Coupling of COBRA-TF to nTRACER for full core high fidelity analysis of VVERs. In International conference on physics of reactors 2022 (PHYSOR 2022) (pp. 586-595). American Nuclear Society. |
| Validation of the novel core solver nTRACER/COBRA-TF for full core high fidelity cycle analysis of VVERs
Papadionysiou, M., Kim, S., Hursin, M., Vasiliev, A., Ferroukhi, H., Pautz, A., & Joo, H. G. (2022). Validation of the novel core solver nTRACER/COBRA-TF for full core high fidelity cycle analysis of VVERs. Nuclear Engineering and Design, 398, 111946 (16 pp.). https://doi.org/10.1016/j.nucengdes.2022.111946 |
