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Imaging neutron capture cross sections: i-TED proof-of-concept and future prospects based on Machine-Learning techniques
Babiano-Suárez, V., Lerendegui-Marco, J., Balibrea-Correa, J., Caballero, L., Calvo, D., Ladarescu, I., … Žugec, P. (2021). Imaging neutron capture cross sections: i-TED proof-of-concept and future prospects based on Machine-Learning techniques. European Physical Journal A: Hadrons and Nuclei, 57(6), 197 (17 pp.). https://doi.org/10.1140/epja/s10050-021-00507-7
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
Recent developments in PSI BEPU analysis for SPERT-III RIA transient: ND uncertainty breakdown and kinetic parameters uncertainty assessment
Dokhane, A., Hursin, M., Vasiliev, A., Rochman, D., & Ferroukhi, H. (2021). Recent developments in PSI BEPU analysis for SPERT-III RIA transient: ND uncertainty breakdown and kinetic parameters uncertainty assessment. Nuclear Engineering and Design, 382, 111378 (14 pp.). https://doi.org/10.1016/j.nucengdes.2021.111378
Nuclear data uncertainty quantification in criticality safety evaluations for spent nuclear fuel geological disposal
Frankl, M., Hursin, M., Rochman, D., Vasiliev, A., & Ferroukhi, H. (2021). Nuclear data uncertainty quantification in criticality safety evaluations for spent nuclear fuel geological disposal. Applied Sciences, 11(14), 6499 (19 pp.). https://doi.org/10.3390/app11146499
Impact of various source of covariance information on integral parameters uncertainty during depletion calculations with CASMO-5
Hursin, M., Rochman, D., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2021). Impact of various source of covariance information on integral parameters uncertainty during depletion calculations with CASMO-5. 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. 09005 (10 pp.). https://doi.org/10.1051/epjconf/202124709005
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
Development of 3D pin-by-pin core solver tortin and coupling with thermal-hydraulics
Mala, P., Pautz, A., Ferroukhi, H., & Vasiliev, A. (2021). Development of 3D pin-by-pin core solver tortin and coupling with thermal-hydraulics. 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. 02034 (8 pp.). https://doi.org/10.1051/epjconf/202124702034
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
Coupling of nTRACER to COBRA-TF for high-fidelity analysis of VVERs
Papadionysiou, M., Seongchan, K., Hursin, M., Vasiliev, A., Ferroukhi, H., Pautz, A., & Joo, H. G. (2021). Coupling of nTRACER to COBRA-TF for high-fidelity analysis of VVERs. 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. 02008 (8 pp.). https://doi.org/10.1051/epjconf/202124702008
Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems
Pelloni, S., & Rochman, D. (2021). Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems. Annals of Nuclear Energy, 163, 108590 (12 pp.). https://doi.org/10.1016/j.anucene.2021.108590
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
Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise
Pázsit, I., Torres, L. A., Hursin, M., Nylén, H., Dykin, V., & Montalvo, C. (2021). Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise. Progress in Nuclear Energy, 138, 103805 (11 pp.). https://doi.org/10.1016/j.pnucene.2021.103805
Reconstructing the axial void velocity profile in BWRS from measurements of the in-core neutron noise
Pázsit, I., Hursin, M., Nylén, H., & Dykin, V. (2021). Reconstructing the axial void velocity profile in BWRS from measurements of the in-core neutron noise. 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. 02013 (8 pp.). https://doi.org/10.1051/epjconf/202124702013
Analysis for the ARIANE BM1 and BM3 samples: nuclide inventory and decay heat
Rochman, D., Vasiliev, A., Ferroukhi, H., & Hursin, M. (2021). Analysis for the ARIANE BM1 and BM3 samples: nuclide inventory and decay heat. EPJ Nuclear Sciences and Technologies, 7, 18 (24 pp.). https://doi.org/10.1051/epjn/2021017
Analysis for the ARIANE GU1 sample: nuclide inventory and decay heat
Rochman, D., Vasiliev, A., Ferroukhi, H., & Hursin, M. (2021). Analysis for the ARIANE GU1 sample: nuclide inventory and decay heat. Annals of Nuclear Energy, 160, 108359 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108359
Analysis for the ARIANE GU3 sample: nuclide inventory and decay heat
Rochman, D., Vasiliev, A., Ferroukhi, H., Hursin, M., Ichou, R., Taforeau, J., & Simeonov, T. (2021). Analysis for the ARIANE GU3 sample: nuclide inventory and decay heat. EPJ Nuclear Sciences and Technologies, 7, 14 (24 pp.). https://doi.org/10.1051/epjn/2021013
Fission yields and cross sections: correlated or not?
Rochman, D. A., & Bauge, E. (2021). Fission yields and cross sections: correlated or not? EPJ Nuclear Sciences and Technologies, 7, 5 (9 pp.). https://doi.org/10.1051/epjn/2021005
Impact of H in H<sub>2</sub>O thermal scattering data on depletion calculation: k<sub>∞</sub>, nuclide inventory and decay heat
Rochman, D., Hursin, M., Vasiliev, A., & Ferroukhi, H. (2021). Impact of H in H2O thermal scattering data on depletion calculation: k, nuclide inventory and decay heat. EPJ Nuclear Sciences and Technologies, 7, 24 (8 pp.). https://doi.org/10.1051/epjn/2021027
Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules
Rochman, D., Shama, A., Pudollek, S., Caruso, S., & Pautz, A. (2021). Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules. Nuclear Engineering and Technology, 53(9), 2816-2829. https://doi.org/10.1016/j.net.2021.03.013