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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
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 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.
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). .
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.
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 Proceedings of the international conference on physics of reactors, PHYSOR 2022. International conference on physics of reactors (pp. 2762-2772). https://doi.org/10.13182/PHYSOR22-37760
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). .
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.
Coupling of nTRACER to COBRA-TF 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 nTRACER to COBRA-TF for full core high-fidelity analysis of VVERs. In Proceedings of the international conference on physics of reactors, PHYSOR 2022. International conference on physics of reactors (pp. 586-595). https://doi.org/10.13182/PHYSOR22-37390
Bias and uncertainty considerations for trace predictions of RBHT reflood experiments
Perret, G., Clifford, I., & Ferroukhi, H. (2022). Bias and uncertainty considerations for trace predictions of RBHT reflood experiments. In 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19) (p. 19001 (14 pp.). American Nuclear Society.
Methodology for high-fidelity deterministic modelling of Swiss LWR fuel assemblies
Bernal, A., Pecchia, M., Rochman, D., Vasiliev, A., & Ferroukhi, H. (2021). Methodology for high-fidelity deterministic modelling of Swiss LWR fuel assemblies. In M. Margulis & P. Blaise (Eds.), EPJ web of conferences: Vol. 247. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future (p. 06011 (8 pp.). https://doi.org/10.1051/epjconf/202124706011
Impact of various source of covariance information on integral parameters uncertainty during depletion calculations with CASMO-5
Hursin, M., Rochman, D., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2021). Impact of various source of covariance information on integral parameters uncertainty during depletion calculations with CASMO-5. In M. Margulis & P. Blaise (Eds.), EPJ web of conferences: Vol. 247. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future (p. 09005 (10 pp.). https://doi.org/10.1051/epjconf/202124709005
Extension of Falcon's modelling capabilities to dry storage: development of a new model for hydrogen behavior in duplex claddings
Konarski, P., Cozzo, C., Khostov, G., & Ferroukhi, H. (2021). Extension of Falcon's modelling capabilities to dry storage: development of a new model for hydrogen behavior in duplex claddings. In TopFuel2021 (p. (10 pp.). European Nuclear Society.
Development of 3D pin-by-pin core solver tortin and coupling with thermal-hydraulics
Mala, P., Pautz, A., Ferroukhi, H., & Vasiliev, A. (2021). Development of 3D pin-by-pin core solver tortin and coupling with thermal-hydraulics. In M. Margulis & P. Blaise (Eds.), EPJ web of conferences: Vol. 247. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future (p. 02034 (8 pp.). https://doi.org/10.1051/epjconf/202124702034
Coupling of nTRACER to COBRA-TF for high-fidelity analysis of VVERs
Papadionysiou, M., Seongchan, K., Hursin, M., Vasiliev, A., Ferroukhi, H., Pautz, A., & Joo, H. G. (2021). Coupling of nTRACER to COBRA-TF for high-fidelity analysis of VVERs. In M. Margulis & P. Blaise (Eds.), EPJ web of conferences: Vol. 247. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future (p. 02008 (8 pp.). https://doi.org/10.1051/epjconf/202124702008
Neutron emission measurements of PWR spent fuel segments and preliminary validation of depletion calculations
Perret, G., Rochman, D., Vasiliev, A., & Ferroukhi, H. (2021). Neutron emission measurements of PWR spent fuel segments and preliminary validation of depletion calculations. In M. Margulis & P. Blaise (Eds.), EPJ web of conferences: Vol. 247. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future (p. 10004 (10 pp.). https://doi.org/10.1051/epjconf/202124710004
Enhancement of validation studies for reactor dosimetry and activation predictions with the nuclear data sampling methodology
Vasiliev, A., Pecchia, M., Rochman, D., & Ferroukhi, H. (2021). Enhancement of validation studies for reactor dosimetry and activation predictions with the nuclear data sampling methodology. In M. Margulis & P. Blaise (Eds.), EPJ web of conferences: Vol. 247. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future (p. 10021 (8 pp.). https://doi.org/10.1051/epjconf/202124710021
 

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