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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
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
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
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
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
Global sensitivity analysis and bayesian calibration on a series of reflood experiments with varying boundary conditions
Perret, G., Wicaksono, D., Clifford, I. D., & Ferroukhi, H. (2022). Global sensitivity analysis and bayesian calibration on a series of reflood experiments with varying boundary conditions. Nuclear Technology, 208(4), 711-722. https://doi.org/10.1080/00295450.2021.1936879
Development of a semi-implicit contact methodology for finite volume stress solvers
Scolaro, A., Fiorina, C., Clifford, I., & Pautz, A. (2022). Development of a semi-implicit contact methodology for finite volume stress solvers. International Journal for Numerical Methods in Engineering, 123(2), 309-338. https://doi.org/10.1002/nme.6857
Towards coupling conventional with high-fidelity fuel behavior analysis tools
Scolaro, A., Van Uffelen, P., Schubert, A., Fiorina, C., Brunetto, E., Clifford, I., & Pautz, A. (2022). Towards coupling conventional with high-fidelity fuel behavior analysis tools. Progress in Nuclear Energy, 152, 104357 (12 pp.). https://doi.org/10.1016/j.pnucene.2022.104357
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
Investigation on the effect of eccentricity for fuel disc irradiation tests
Scolaro, A., Van Uffelen, P., Fiorina, C., Schubert, A., Clifford, I., & Pautz, A. (2021). Investigation on the effect of eccentricity for fuel disc irradiation tests. Nuclear Engineering and Technology, 53(5), 1602-1611. https://doi.org/10.1016/j.net.2020.11.003
The OFFBEAT multi-dimensional fuel behavior solver
Scolaro, A., Clifford, I., Fiorina, C., & Pautz, A. (2020). The OFFBEAT multi-dimensional fuel behavior solver. Nuclear Engineering and Design, 358, 110416 (16 pp.). https://doi.org/10.1016/j.nucengdes.2019.110416
Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs
Clifford, I., Pecchia, M., Mukin, R., Cozzo, C., Ferroukhi, H., & Gorzel, A. (2019). Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs. Annals of Nuclear Energy, 130, 440-451. https://doi.org/10.1016/j.anucene.2019.03.017
Global sensitivity and registration strategy for temperature profile of reflood experiment simulations
Perret, G., Wicaksono, D., Clifford, I. D., & Ferroukhi, H. (2019). Global sensitivity and registration strategy for temperature profile of reflood experiment simulations. Nuclear Technology, 205(12), 1638-1651. https://doi.org/10.1080/00295450.2019.1591154
Simulation of the microfluidic mixing and the droplet generation for 3D printing of nuclear fuels
Shama, A., Pouchon, M. A., & Clifford, I. (2019). Simulation of the microfluidic mixing and the droplet generation for 3D printing of nuclear fuels. Additive Manufacturing, 26, 1-14. https://doi.org/10.1016/j.addma.2018.12.011
On the characteristics of the flow and heat transfer in the core bypass region of a PWR
Clifford, I., Pecchia, M., Puragliesi, R., Vasiliev, A., & Ferroukhi, H. (2018). On the characteristics of the flow and heat transfer in the core bypass region of a PWR. Nuclear Engineering and Design, 330, 117-128. https://doi.org/10.1016/j.nucengdes.2018.01.039