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Operational modal analysis for characterization of mechanical and thermal-hydraulic fluctuations in simulated neutron noise
Torres Delgado, L. A., Verma, V., Montalvo, C., Dokhane, A., & García-Berrocal, A. (2021). Operational modal analysis for characterization of mechanical and thermal-hydraulic fluctuations in simulated neutron noise. Nuclear Engineering and Design, 373, 111017 (18 pp.). https://doi.org/10.1016/j.nucengdes.2020.111017
Studies of reactor noise response to vibrations of reactor internals and thermal-hydraulic fluctuations in PWRs
Verma, V., Chionis, D., Dokhane, A., & Ferroukhi, H. (2021). Studies of reactor noise response to vibrations of reactor internals and thermal-hydraulic fluctuations in PWRs. Annals of Nuclear Energy, 157, 108212 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108212
Development and verification of a methodology for neutron noise response to fuel assembly vibrations
Chionis, D., Dokhane, A., Belblidia, L., Ferroukhi, H., Girardin, G., & Pautz, A. (2020). Development and verification of a methodology for neutron noise response to fuel assembly vibrations. Annals of Nuclear Energy, 147, 107669 (15 pp.). https://doi.org/10.1016/j.anucene.2020.107669
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., Polhus, J., … Pautz, A. (2020). Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX. In Proceedings of the PHYSOR 2020 (p. 1573 (9 pp.). Nuclear Energy Group.
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. (2020). CORE SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements. In Proceedings of the PHYSOR 2020 (p. 1207 (9 pp.). Nuclear Energy Group.
Reconstructing the axial void velocity profile in BWRs from measurements of the in-core neutron noise
Pázsit, I., Hursin, M., Nylén, H., & Dykin, V. (2020). Reconstructing the axial void velocity profile in BWRs from measurements of the in-core neutron noise. In Proceedings of the PHYSOR 2020 (p. 1337 (8 pp.). Nuclear Energy Group.
Modelling and analysis of fuel assembly vibrational modes in PWRs using SIMULATE-3K
Verma, V., Chionis, D., Dokhane, A., & Ferroukhi, H. (2020). Modelling and analysis of fuel assembly vibrational modes in PWRs using SIMULATE-3K. In Proceedings of the PHYSOR 2020 (p. 1270 (8 pp.). Nuclear Energy Group.
Spatial localization of perturbation propagation in LWRs using causality and connectivity analysis
Chionis, D., Dokhane, A., Ferroukhi, H., & Pautz, A. (2019). Spatial localization of perturbation propagation in LWRs using causality and connectivity analysis. In International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019) (pp. 1960-1969). American Nuclear Society (ANS).
Towards the validation of neutron noise simulators: qualification of data acquisition systems
Rais, A., Lamirand, V., Pakari, O., Laureau, A., Pohlus, J., Pohl, C., … Pautz, A. (2019). Towards the validation of neutron noise simulators: qualification of data acquisition systems. In International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019) (pp. 2638-2647). American Nuclear Society (ANS).
Neutron noise analysis of simulated mechanical and thermal-hydraulic perturbations in a PWR core
Torres, L. A., Chionis, D., Montalvo, C., Dokhane, A., & García-Berrocal, A. (2019). Neutron noise analysis of simulated mechanical and thermal-hydraulic perturbations in a PWR core. Annals of Nuclear Energy, 126, 242-252. https://doi.org/10.1016/j.anucene.2018.11.032
Assessment of the neutron noise induced by stationary fuel assembly vibrations in a light water reactor
Verma, V., Demazière, C., Vinai, P., Ricciardi, G., & Jacqmin, R. (2019). Assessment of the neutron noise induced by stationary fuel assembly vibrations in a light water reactor. In International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019) (pp. 1124-1133). American Nuclear Society (ANS).
PWR neutron noise phenomenology: part I - simulation of stochastic phenomena with simulate-3K
Chionis, D., Dokhane, A., Ferroukhi, H., Girardin, G., & Pautz, A. (2018). PWR neutron noise phenomenology: part I - simulation of stochastic phenomena with simulate-3K. In Proceedings of the PHYSOR 2018 (pp. 1001-1012). American Nuclear Society.
PWR neutron noise phenomenology: part II - qualitative comparison against plant data
Chionis, D., Dokhane, A., Ferroukhi, H., Girardin, G., & Pautz, A. (2018). PWR neutron noise phenomenology: part II - qualitative comparison against plant data. In Proceedings of the PHYSOR 2018 (pp. 1013-1024). American Nuclear Society.
Current mode neutron noise measurements in the zero power reactor CROCUS
Pakari, O., Lamirand, V., Perret, G., Braun, L., Frajtag, P., & Pautz, A. (2018). Current mode neutron noise measurements in the zero power reactor CROCUS. In A. Lyoussi, M. Carette, M. Giot, P. Le Dû, C. Reynard-Carette, M. Schyns, & L. Vermeeren (Eds.), EPJ web of conferences: Vol. 170. ANIMMA 2017 - advancements in nuclear instrumentation measurement methods and their applications (p. 04017 (5 pp.). https://doi.org/10.1051/epjconf/201817004017
Kinetic parameter measurements in the CROCUS reactor using current mode instrumentation
Pakari, O., Lamirand, V., Perret, G., Frajtag, P., & Pautz, A. (2018). Kinetic parameter measurements in the CROCUS reactor using current mode instrumentation. IEEE Transactions on Nuclear Science, 65(9), 2456-2460. https://doi.org/10.1109/TNS.2018.2831180
SIMULATE-3K analyses of neutron noise response to fuel assembly vibrations and thermal-hydraulics parameters fluctuations
Chionis, D., Dokhane, A., Belblidia, L., Pecchia, M., Giardin, G., Ferroukhi, H., & Pautz, A. (2017). SIMULATE-3K analyses of neutron noise response to fuel assembly vibrations and thermal-hydraulics parameters fluctuations. In Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017) (p. P289 (8 pp.). Korean Nuclear Society.
Kinetic parameter measurements in the Minerve reactor
Perret, G., Geslot, B., Gruel, A., Blaise, P., Di-Salvo, J., De Izarra, G., … Pautz, A. (2017). Kinetic parameter measurements in the Minerve reactor. IEEE Transactions on Nuclear Science, 64(1), 724-734. https://doi.org/10.1109/TNS.2016.2637569
Delayed neutron fraction and prompt decay constant measurement in the Minerve reactor using the PSI instrumentation
Perret, G. (2015). Delayed neutron fraction and prompt decay constant measurement in the Minerve reactor using the PSI instrumentation. In Vol. 1. 2015 4th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications, ANIMMA 2015 (p. 7465533). https://doi.org/10.1109/ANIMMA.2015.7465533