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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
Comparison of calculated and measured spent nuclear fuel decay heat with CASMO5, <em>SNF</em> and standard methods
Rochman, D., Taforeau, J., Simeonov, T., & Shama, A. (2023). Comparison of calculated and measured spent nuclear fuel decay heat with CASMO5, SNF and standard methods. Nuclear Engineering and Design, 410, 112392 (9 pp.). https://doi.org/10.1016/j.nucengdes.2023.112392
Analysis of transient measurements with thermal feedback and coupled TRACE/PARCS calculations performed on the BME Training Reactor
Ványi, A. S., Hursin, M., & Czifrus, S. (2023). Analysis of transient measurements with thermal feedback and coupled TRACE/PARCS calculations performed on the BME Training Reactor. Annals of Nuclear Energy, 194, 110072 (15 pp.). https://doi.org/10.1016/j.anucene.2023.110072
Thermal-hydraulic measurements and TRACE system code analysis performed on the natural circulation cooled BME Training Reactor
Ványi, A. S., Hursin, M., Aszódi, A., Adorján, L., Biró, B., Magyar, B., … Czifrus, S. (2023). Thermal-hydraulic measurements and TRACE system code analysis performed on the natural circulation cooled BME Training Reactor. Annals of Nuclear Energy, 189, 109839 (12 pp.). https://doi.org/10.1016/j.anucene.2023.109839
Blind benchmark exercise for spent nuclear fuel decay heat
Jansson, P., Bengtsson, M., Bäckström, U., Álvarez-Velarde, F., Čalič, D., Caruso, S., … Sjöland, A. (2022). Blind benchmark exercise for spent nuclear fuel decay heat. Nuclear Science and Engineering, 196(9), 1125-1145. https://doi.org/10.1080/00295639.2022.2053489
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
Overview of the OECD-NEA expert group on multi-physics experimental data, benchmarks and validation
Valentine, T., Avramova, M., Fleming, M., Hursin, M., Ivanov, K., Petruzzi, A., … Velkov, K. (2021). Overview of the OECD-NEA expert group on multi-physics experimental data, benchmarks and validation. 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. 06048 (8 pp.). https://doi.org/10.1051/epjconf/202124706048
Enhancement of validation studies for reactor dosimetry and activation predictions with the nuclear data sampling methodology
Vasiliev, A., Pecchia, M., Rochman, D., & Ferroukhi, H. (2021). Enhancement of validation studies for reactor dosimetry and activation predictions with the nuclear data sampling methodology. 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. 10021 (8 pp.). https://doi.org/10.1051/epjconf/202124710021
Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor
Ványi, A. S., Babcsány, B., Böröczki, Z. I., Horváth, A., Hursin, M., Szieberth, M., & Czifrus, S. (2021). Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor. Annals of Nuclear Energy, 155, 108144 (15 pp.). https://doi.org/10.1016/j.anucene.2021.108144
Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE
Mukin, R., Clifford, I., Zerkak, O., & Ferroukhi, H. (2018). Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE. Nuclear Engineering and Technology, 50(3), 356-367. https://doi.org/10.1016/j.net.2017.12.005
On the options for incorporating nuclear data uncertainties in criticality safety assessments for LWR fuel
Vasiliev, A., Rochman, D., Pecchia, M., & Ferroukhi, H. (2018). On the options for incorporating nuclear data uncertainties in criticality safety assessments for LWR fuel. Annals of Nuclear Energy, 116, 57-68. https://doi.org/10.1016/j.anucene.2018.01.046
Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model
Grimm, P., Hursin, M., Perret, G., Siefman, D., & Ferroukhi, H. (2017). Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model. Progress in Nuclear Energy, 101, 280-287. https://doi.org/10.1016/j.pnucene.2017.03.018
Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19
Hursin, M., Bogetic, S., Dohkane, A., Canepa, S., Zerkak, O., Ferroukhi, H., & Pautz, A. (2017). Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19. Annals of Nuclear Energy, 101, 559-575. https://doi.org/10.1016/j.anucene.2016.11.001
Validation of Monte Carlo based burnup codes against LWR-PROTEUS Phase-II experimental data
Pecchia, M., Wicaksono, D., Grimm, P., Vasiliev, A., Perret, G., Ferroukhi, H., & Pautz, A. (2016). Validation of Monte Carlo based burnup codes against LWR-PROTEUS Phase-II experimental data. Annals of Nuclear Energy, 97, 153-164. https://doi.org/10.1016/j.anucene.2016.07.001
Exploring stochastic sampling in nuclear data uncertainties assessment for reactor physics applications and validation studies
Vasiliev, A., Rochman, D. I., Pecchia, M., & Ferroukhi, H. (2016). Exploring stochastic sampling in nuclear data uncertainties assessment for reactor physics applications and validation studies. Energies, 9(12), 1039 (18 pp.). https://doi.org/10.3390/en9121039
Towards a consolidated approach for the validation of plant system codes and models: case study for a BWR fast depressurisation event
Epiney, A., Canepa, S., Zerkak, O., & Ferroukhi, H. (2015). Towards a consolidated approach for the validation of plant system codes and models: case study for a BWR fast depressurisation event. In 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16) (pp. 2157-2170). American Nuclear Society.
Updated validation of the PSI criticality safety evaluation methodology using MCNPX2.7 and ENDF/B-VII.1
Pecchia, M., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2014). Updated validation of the PSI criticality safety evaluation methodology using MCNPX2.7 and ENDF/B-VII.1 (p. 1105709 (15 pp.). Presented at the International conference on physics of reactors (PHYSOR 2014). .