| 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 |
| Choked-flow model parameter uncertainty determination using hierarchical calibration
Perret, G., Clifford, I. D., & Ferroukhi, H. (2024). Choked-flow model parameter uncertainty determination using hierarchical calibration. Annals of Nuclear Energy, 207, 110672 (12 pp.). https://doi.org/10.1016/j.anucene.2024.110672 |
| 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 the choked flow model of RELAP5 for the application of inverse quantification methods
Freixa, J., Martínez-Quiroga, V., & Perret, G. (2023). Assessment of the choked flow model of RELAP5 for the application of inverse quantification methods. In 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 5426-5439). https://doi.org/10.13182/NURETH20-40674 |
| 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 |
| Development of a multi-channel gamma-blind fast neutron detector based on wavelength shifting fibers embedded in a ZnS:Ag epoxy mixture
Wolfertz, A., Adams, R., Perret, G., & Lamirand, V. (2023). Development of a multi-channel gamma-blind fast neutron detector based on wavelength shifting fibers embedded in a ZnS:Ag epoxy mixture. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 1053, 168385 (12 pp.). https://doi.org/10.1016/j.nima.2023.168385 |
| Non-destructive analysis of spent fuel samples using a gamma-blind fast neutron detector
Wolfertz, A., Perret, G., & Adams, R. (2023). Non-destructive analysis of spent fuel samples using a gamma-blind fast neutron detector. Annals of Nuclear Energy, 188, 109792 (10 pp.). https://doi.org/10.1016/j.anucene.2023.109792 |
| 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. |
| 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 |
| Validation of axial void profile measured by neutron noise techniques in crocus
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2021). Validation of axial void profile measured by neutron noise techniques in crocus. 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. 08004 (8 pp.). https://doi.org/10.1051/epjconf/202124708004 |
| Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX
Lamirand, V., Rais, A., Pakari, O., Hursin, M., Laureau, A., Pohlus, J., … Pautz, A. (2021). Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX. 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. 21010 (9 pp.). https://doi.org/10.1051/epjconf/202124721010 |
| Core SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements
Mylonakis, A. G., Demazière, C., Vinai, P., Lamirand, V., Rais, A., Pakari, O., … Pautz, A. (2021). Core SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements. 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. 21006 (9 pp.). https://doi.org/10.1051/epjconf/202124721006 |
| 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 |
| Sea container inspection with tagged neutrons
Pérot, B., Carasco, C., Eléon, C., Bernard, S., Sardet, A., El Kanawati, W., … Gierlik, M. (2021). Sea container inspection with tagged neutrons. EPJ Nuclear Sciences and Technologies, 7, 6 (37 pp.). https://doi.org/10.1051/epjn/2021004 |
| Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2020). Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques. Nuclear Technology, 206(10), 1566-1583. https://doi.org/10.1080/00295450.2019.1701906 |
| Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX
Lamirand, V., Rais, A., Hübner, S., Lange, C., Pohlus, J., Paquee, U., … Pautz, A. (2020). Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX. In A. Lyoussi, M. Giot, M. Carette, I. Jenčič, C. Reynard-Carette, L. Vermeeren, … P. Le Dû (Eds.), EPJ web of conferences: Vol. 225. ANIMMA 2019 - advancements in nuclear instrumentation measurement methods and their applications (p. 04023 (6 pp.). https://doi.org/10.1051/epjconf/202022504023 |
| The COLIBRI experimental program in the CROCUS reactor: characterization of the fuel rods oscillator
Lamirand, V., Frajtag, P., Godat, D., Pakari, O., Laureau, A., Rais, A., … Pautz, A. (2020). The COLIBRI experimental program in the CROCUS reactor: characterization of the fuel rods oscillator. In A. Lyoussi, M. Giot, M. Carette, I. Jenčič, C. Reynard-Carette, L. Vermeeren, … P. Le Dû (Eds.), EPJ web of conferences: Vol. 225. ANIMMA 2019 - advancements in nuclear instrumentation measurement methods and their applications (p. 04020 (5 pp.). https://doi.org/10.1051/epjconf/202022504020 |
| Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments
Siefman, D., Hursin, M., Perret, G., & Pautz, A. (2020). Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments. Progress in Nuclear Energy, 121, 103245 (9 pp.). https://doi.org/10.1016/j.pnucene.2020.103245 |
| Assessment of representativity of the PETALE experiments for validation of Swiss LWRs ex-core dosimetry calculations
Vasiliev, A., Pecchia, M., Rochman, D., Perret, G., Ferroukhi, H., Laureau, A., … Pautz, A. (2020). Assessment of representativity of the PETALE experiments for validation of Swiss LWRs ex-core dosimetry calculations. In Z. Ge, N. Shu, Y. Chen, W. Wang, & H. Zhang (Eds.), EPJ web of conferences: Vol. 239. ND 2019: international conference on nuclear data for science and technology (p. 22001 (6 pp.). https://doi.org/10.1051/epjconf/202023922001 |
