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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 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
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
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
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
Results of the <sup>244</sup>Cm, <sup>246</sup>Cm and <sup>248</sup>Cm neutron-induced capture cross sections measurements at EAR1 and EAR2 of the n_TOF facility
Alcayne, V., Mendoza, E., Cano-Ott, D., Kimura, A., Aberle, O., Amaducci, S., … Žugec, P. (2023). Results of the 244Cm, 246Cm and 248Cm neutron-induced capture cross sections measurements at EAR1 and EAR2 of the n_TOF facility. In C. M. Mattoon, R. Vogt, J. Escher, & I. Thompson (Eds.), EPJ web conferences: Vol. 284. 15th international conference on nuclear data for science and technology (ND2022) (p. 01009 (6 pp.). https://doi.org/10.1051/epjconf/202328401009
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
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
Noise analysis techniques of in-core modulation experiments for the European project CORTEX
Ambrožič, K., Lamirand, V., Hübner, S., Hursin, M., Rais, A., Pakari, O., … Pautz, A. (2020). Noise analysis techniques of in-core modulation experiments for the European project CORTEX. In L. Snoj & A. Čufar (Eds.), NENE 2020 conference proceedings (p. 212 (8 pp.). Nuclear Society of Slovenia.
High resolution <sup>80</sup>Se(n,<em>γ</em>) cross section measurement at CERN n_TOF
Babiano-Suarez, V., Balibrea-Correa, J., Caballero-Ontanaya, L., Domingo-Pardo, C., Ladarescu, I., Lerendegui-Marco, J., … Žugec, P. (2023). High resolution 80Se(n,γ) cross section measurement at CERN n_TOF. In C. M. Mattoon, R. Vogt, J. Escher, & I. Thompson (Eds.), EPJ web conferences: Vol. 284. 15th international conference on nuclear data for science and technology (ND2022) (p. 01001 (6 pp.). https://doi.org/10.1051/epjconf/202328401001
First <sup>80</sup>Se(n,γ) cross section measurement with high resolution in the full stellar energy range 1 eV - 100 keV and its astrophysical implications for the s-process
Babiano-Suarez, V., Balibrea-Correa, J., Caballero-Ontanaya, L., Domingo-Pardo, C., Ladarescu, I., Lerendegui-Marco, J., … Žugec, P. (2022). First 80Se(n,γ) cross section measurement with high resolution in the full stellar energy range 1 eV - 100 keV and its astrophysical implications for the s-process. In W. Liu, Y. Wang, B. Guo, X. Tang, & S. Zeng (Eds.), 16th symposium on nuclei in the cosmos, NIC-XVI 2021. Symposium on nuclei in the cosmos (p. 11026 (8 pp.). https://doi.org/10.1051/epjconf/202226011026
Experimental studies on retention of iodine in a wet scrubber
Beghi, I., Lind, T., & Prasser, H. M. (2018). Experimental studies on retention of iodine in a wet scrubber. Nuclear Engineering and Design, 326, 234-243. https://doi.org/10.1016/j.nucengdes.2017.11.025
Effect of hydrodynamics on the retention of iodine in a wet scrubber
Beghi, I., Tietze, S., Lind, T., & Prasser, H. M. (2018). Effect of hydrodynamics on the retention of iodine in a wet scrubber. In Vol. 1. International congress on advances in nuclear power plants (ICAPP 2018) (pp. 302-309). 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
Droplet size distribution in a full-scale rectangular self-priming Venturi scrubber with liquid film injection
Breitenmoser, D., Papadopoulos, P., Lind, T., & Prasser, H. M. (2021). Droplet size distribution in a full-scale rectangular self-priming Venturi scrubber with liquid film injection. International Journal of Multiphase Flow, 142, 103694 (15 pp.). https://doi.org/10.1016/j.ijmultiphaseflow.2021.103694
High resolution measurements with miniature neutron scintillators in the SUR-100 zero power reactor
Brunetto, E., Vitullo, F., Lamirand, V., Ambrožič, K., Godat, D., Buck, M., … Pautz, A. (2021). High resolution measurements with miniature neutron scintillators in the SUR-100 zero power reactor. In A. Lyoussi, M. Carette, R. Hodák, I. Jenčič, P. Le Dû, S. Pospíšil, … L. Vermeeren (Eds.), EPJ web of conferences: Vol. 253. ANIMMA 2021 - advancements in nuclear instrumentation measurement methods and their applications (p. 04029 (8 pp.). https://doi.org/10.1051/epjconf/202125304029
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
Assessing the effects of switching from multi-channel to three-dimensional nodalisations of the core in TRACE
Clifford, I., & Ferroukhi, H. (2021). Assessing the effects of switching from multi-channel to three-dimensional nodalisations of the core in TRACE. Nuclear Engineering and Design, 383, 111446 (15 pp.). https://doi.org/10.1016/j.nucengdes.2021.111446
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.
 

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