| 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 |