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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
A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity
Baccou, J., Glantz, T., Ghione, A., Sargentini, L., Fillion, P., Damblin, G., … Adorni, M. (2024). A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity. Nuclear Engineering and Design, 421, 113035 (16 pp.). https://doi.org/10.1016/j.nucengdes.2024.113035
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
State of the art for thermal-hydraulic analysis of pressurised thermal shock scenarios
Clifford, I., Kral, P., Vyskocil, L., Pistora, V., Trewin, R., Filonova, Y., … Roy, J. (2023). State of the art for thermal-hydraulic analysis of pressurised thermal shock scenarios. In 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 5778-5790). https://doi.org/10.13182/NURETH20-40247
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.
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
CFD simulations of the UPTF-TRAM test C1
Fogliatto, E., & Clifford, I. (2023). CFD simulations of the UPTF-TRAM test C1. In 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 606-617). https://doi.org/10.13182/NURETH20-40211
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
LTO modifications to reduce the pts issue - results of TH calculations in the context of the APAL European project
Puustinen, M., Patel, G., Kral, P., Nikl, T., Clifford, I., Trewin, R., … Vyshemirskyi, M. (2023). LTO modifications to reduce the pts issue - results of TH calculations in the context of the APAL European project. In Proceedings 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 282-295). https://doi.org/10.13182/NURETH20-40206
Evaluation of uncertainties in thermal-hydraulic analyses of PTS for the APAL European project
Trewin, R., Prošek, A., Kral, P., Clifford, I., Perret, G., Hartung, J., … Filonova, Y. (2023). Evaluation of uncertainties in thermal-hydraulic analyses of PTS for the APAL European project. In Proceedings of the 20th international topical meeting on nuclear reactor thermal hydraulics (pp. 5791-5805). https://doi.org/10.13182/NURETH20-40288
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). .
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
On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives
Fiorina, C., Clifford, I., Kelm, S., & Lorenzi, S. (2022). On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives. Nuclear Engineering and Design, 387, 111604 (15 pp.). https://doi.org/10.1016/j.nucengdes.2021.111604
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.
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