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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
From medical imaging to radiomics: role of data science for advancing precision health
Capobianco, E., & Dominietto, M. (2020). From medical imaging to radiomics: role of data science for advancing precision health. Journal of Personalized Medicine, 10(1), 15 (13 pp.). https://doi.org/10.3390/jpm10010015
CFD prediction of hydrogen passive autocatalytic recombiner performance under counter-current flow conditions
Halouane, Y., & Dehbi, A. (2020). CFD prediction of hydrogen passive autocatalytic recombiner performance under counter-current flow conditions. International Journal of Hydrogen Energy, 45(16), 10247-10256. https://doi.org/10.1016/j.ijhydene.2020.01.189
Neutron emission measurements of PWR spent fuel segments and preliminary validation of depletion calculations
Perret, G., Rochman, D., Vasiliev, A., & Ferroukhi, H. (2020). Neutron emission measurements of PWR spent fuel segments and preliminary validation of depletion calculations. In Proceedings of the PHYSOR 2020 (p. 1174 (10 pp.). Nuclear Energy Group.
The OFFBEAT multi-dimensional fuel behavior solver
Scolaro, A., Clifford, I., Fiorina, C., & Pautz, A. (2020). The OFFBEAT multi-dimensional fuel behavior solver. Nuclear Engineering and Design, 358, 110416 (16 pp.). https://doi.org/10.1016/j.nucengdes.2019.110416
Enhancement of validation studies for reactor dosimetry and ativation predictions with the nuclear data sampling methodology
Vasiliev, A., Pecchia, M., Rochman, D., & Ferroukhi, H. (2020). Enhancement of validation studies for reactor dosimetry and ativation predictions with the nuclear data sampling methodology. In Proceedings of the PHYSOR 2020 (p. 1427 (8 pp.). Nuclear Energy Group.
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
Guidance on validation and qualification of processes and operations involving radiopharmaceuticals
Todde, S., Peitl, P. K., Elsinga, P., Koziorowski, J., Ferrari, V., Ocak, E. M., … Behe, M. (2017). Guidance on validation and qualification of processes and operations involving radiopharmaceuticals. EJNMMI Radiopharmacy and Chemistry, 2(1), 8 (29 pp.). https://doi.org/10.1186/s41181-017-0025-9
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
Validation of Monte-Carlo methods for generation time and delayed neutron fraction predictions
Perret, G., Blaise, P., Messaoudi, N., Geslot, B., Wagemans, J., Baeten, P., … Pautz, A. (2016). Validation of Monte-Carlo methods for generation time and delayed neutron fraction predictions. Annals of Nuclear Energy, 97, 165-170. https://doi.org/10.1016/j.anucene.2016.07.015
Towards the validation of National Risk Assessments against historical observations using a Bayesian approach: application to the Swiss case
Spada, M., Burgherr, P., & Hohl, M. (2016). Towards the validation of National Risk Assessments against historical observations using a Bayesian approach: application to the Swiss case. In M. Stal, D. Sigrist, S. Wahlen, J. Portmann, J. Glover, N. Bernabe, … W. J. Ammann (Eds.), Proceedings of the 6th international disaster and risk conference. IDRC Davos 2016. Extended abstract collection (pp. 583-586). Global Risk Forum GRF Davos.
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
Interaction of lysozyme protein with different sized silica nanoparticles and their resultant structures
Yadav, I., Aswal, V. K., & Kohlbrecher, J. (2016). Interaction of lysozyme protein with different sized silica nanoparticles and their resultant structures. R. Chitra, S. Bhattacharya, & N. K. Sahoo (Eds.), AIP conference proceedings: Vol. 1731. (p. 50093). Presented at the 60th DAE Solid State Physics Symposium 2015. https://doi.org/10.1063/1.4947747
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.
Post-test analysis of OECD/NEA ROSA-2 test 4 using TRACE
Clifford, I., Zerkak, O., & Pautz, A. (2014). Post-test analysis of OECD/NEA ROSA-2 test 4 using TRACE (p. 1182 (12 pp.). Presented at the 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10). .
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). .
In-the-loop validation of fuel cell vehicle control
Wilhelm, E., Fowler, M., Fraser, R. A., & Stevens, M. (2011). In-the-loop validation of fuel cell vehicle control. International Journal of Powertrains, 1(2), 162-178. https://doi.org/10.1504/IJPT.2011.042766