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Measurement of local void fraction of air water flow in the 8 × 8 rod bundle using high-resolution gamma-ray tomography
Ahn, T., Diaz, J., Adams, R., Petrov, V., & Manera, A. (2023). Measurement of local void fraction of air water flow in the 8 × 8 rod bundle using high-resolution gamma-ray tomography. Nuclear Technology. https://doi.org/10.1080/00295450.2023.2197680
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
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
High-fidelity modeling and experiments to inform safety analysis codes for heat pipe microreactors
Bourdot Dutra, C.  da S., Merzari, E., Acierno, J., Kraus, A., Manera, A., Petrov, V., … Shaver, D. (2023). High-fidelity modeling and experiments to inform safety analysis codes for heat pipe microreactors. Nuclear Technology. https://doi.org/10.1080/00295450.2023.2181040
Machine learning based flow regime recognition in helically coiled tubes using X-ray radiography
Breitenmoser, D., Prasser, H. M., Manera, A., & Petrov, V. (2023). Machine learning based flow regime recognition in helically coiled tubes using X-ray radiography. International Journal of Multiphase Flow, 161, 104382 (10 pp.). https://doi.org/10.1016/j.ijmultiphaseflow.2023.104382
FEM heat transfer modelling with tomography-based SiC<sub>f</sub>/SiC unit cell
Cavaliere, A., Marone, F., Cozzo, C., Buchanan, K., Lorrette, C., & Pouchon, M. A. (2023). FEM heat transfer modelling with tomography-based SiCf/SiC unit cell. High Temperatures-High Pressures, 52(2), 95-110. https://doi.org/10.32908/hthp.v52.1281
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
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: first outcomes
Coindreau, O., Herranz, L. E., Bocanegra, R., Ederli, S., Maccari, P., Mascari, F., … Nudi, M. (2023). Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: first outcomes. Annals of Nuclear Energy, 188, 109796 (9 pp.). https://doi.org/10.1016/j.anucene.2023.109796
High-fidelity simulation of mixing phenomena in large enclosures
Coppo Leite, V., Merzari, E., Mao, J., Petrov, V., & Manera, A. (2023). High-fidelity simulation of mixing phenomena in large enclosures. Nuclear Science and Engineering. https://doi.org/10.1080/00295639.2023.2186159
High-resolution X-Ray radiography methods developed for Post-CHF experiment
Diaz, J., Liu, Q., Petrov, V., Manera, A., & Sun, X. (2023). High-resolution X-Ray radiography methods developed for Post-CHF experiment. Nuclear Technology. https://doi.org/10.1080/00295450.2022.2133504
Seeding-free inlet flow distortion measurement by filtered Rayleigh scattering: diagnostic approach and verification
Doll, U., Kapulla, R., Steinbock, J., Dues, M., Migliorini, M., & Zachos, P. K. (2023). Seeding-free inlet flow distortion measurement by filtered Rayleigh scattering: diagnostic approach and verification. In AIAA SCITECH 2023 forum. https://doi.org/10.2514/6.2023-1372
Advances and new ideas for neutron-capture astrophysics experiments at CERN n_TOF
Domingo-Pardo, C., Babiano-Suarez, V., Balibrea-Correa, J., Caballero, L., Ladarescu, I., Lerendegui-Marco, J., … Žugec, P. (2023). Advances and new ideas for neutron-capture astrophysics experiments at CERN n_TOF. European Physical Journal A: Hadrons and Nuclei, 59(1), 8 (11 pp.). https://doi.org/10.1140/epja/s10050-022-00876-7
P2M simulation exercise on past fuel melting irradiation experiments
D’Ambrosi, V., Sercombe, J., Bejaoui, S., Chaieb, A., Baurens, B., Largenton, R., … Peltonen, J. (2023). P2M simulation exercise on past fuel melting irradiation experiments. Nuclear Technology. https://doi.org/10.1080/00295450.2023.2194270
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
Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo
Garbil, R., Hadj Hassine, S. B., Blaise, P., Ferry, C., Sjöland, A., Christensen, P., … Vlassopoulos, E. (2023). Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo. EPJ Nuclear Sciences and Technologies, 9, 2022029 (12 pp.). https://doi.org/10.1051/epjn/2022029
Capability extension of the high-resolution thermal-hydraulic code ESCOT for hexagonal geometry core multiphysics analysis
Gonzalez-Amoros, J., Papadionysiou, M., Kim, S., & Joo, H. G. (2023). Capability extension of the high-resolution thermal-hydraulic code ESCOT for hexagonal geometry core multiphysics analysis. Nuclear Science and Engineering, 197(8), 1634-1655. https://doi.org/10.1080/00295639.2022.2140577
Integration of pool scrubbing research to enhance Source-Term calculations (IPRESCA) project – overview and first results
Gupta, S., Herranz, L. E., Lebel, L. S., Sonnenkalb, M., Pellegrini, M., Marchetto, C., … Kärkelä, T. (2023). Integration of pool scrubbing research to enhance Source-Term calculations (IPRESCA) project – overview and first results. Nuclear Engineering and Design, 404, 112189 (20 pp.). https://doi.org/10.1016/j.nucengdes.2023.112189
Modeling noise experiments performed at AKR-2 and CROCUS zero-power reactors
Hursin, M., Zoia, A., Rouchon, A., Brighenti, A., Zmijarevic, I., Santandrea, S., … Verdú, G. (2023). Modeling noise experiments performed at AKR-2 and CROCUS zero-power reactors. Annals of Nuclear Energy, 194, 110066 (16 pp.). https://doi.org/10.1016/j.anucene.2023.110066
 

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