| Application of backward differential formula and Anderson's method for multigroup diffusion transient equation
Cherezov, A., Vasiliev, A., & Ferroukhi, H. (2025). Application of backward differential formula and Anderson's method for multigroup diffusion transient equation. Annals of Nuclear Energy, 210, 110837 (19 pp.). https://doi.org/10.1016/j.anucene.2024.110837 |
| Fast uncertainty quantification of spent nuclear fuel with neural networks
Albà, A., Adelmann, A., Münster, L., Rochman, D., & Boiger, R. (2024). Fast uncertainty quantification of spent nuclear fuel with neural networks. Annals of Nuclear Energy, 196, 110204 (8 pp.). https://doi.org/10.1016/j.anucene.2023.110204 |
| CORTEX experiments, Part II: Postprocessing of neutron noise time series to determine reliable mean and uncertainties
Ambrožič, K., Knospe, A., Pakari, O., Hübner, S., Hursin, M., Lange, C., … Lamirand, V. (2024). CORTEX experiments, Part II: Postprocessing of neutron noise time series to determine reliable mean and uncertainties. Annals of Nuclear Energy, 208, 110704 (16 pp.). https://doi.org/10.1016/j.anucene.2024.110704 |
| Low precision preconditioning for solving neutron diffusion eigenvalue problem by finite element method
Cherezov, A., Vasiliev, A., & Ferroukhi, H. (2024). Low precision preconditioning for solving neutron diffusion eigenvalue problem by finite element method. Annals of Nuclear Energy, 206, 110575 (11 pp.). https://doi.org/10.1016/j.anucene.2024.110575 |
| Assessment of wall models for coarse-mesh RANS simulations
Fogliatto, E., & Clifford, I. (2024). Assessment of wall models for coarse-mesh RANS simulations. Annals of Nuclear Energy, 209, 110807 (15 pp.). https://doi.org/10.1016/j.anucene.2024.110807 |
| Monte Carlo analysis of BWR geometries using a cycle check-up methodology
Hursin, M., Vasiliev, A., Rochman, D., Dokhane, A., & Ferroukhi, H. (2024). Monte Carlo analysis of BWR geometries using a cycle check-up methodology. Annals of Nuclear Energy, 195, 110170 (17 pp.). https://doi.org/10.1016/j.anucene.2023.110170 |
| CORTEX experiments, Part III: experimental determination of the zero power transfer function of AKR-2 with reliable uncertainties
Knospe, A., Hübner, S., Ambrožič, K., Viebach, M., Lange, C., & Lamirand, V. (2024). CORTEX experiments, Part III: experimental determination of the zero power transfer function of AKR-2 with reliable uncertainties. Annals of Nuclear Energy, 209, 110686 (8 pp.). https://doi.org/10.1016/j.anucene.2024.110686 |
| Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project
Mascari, F., Bersano, A., Massone, M., Agnello, G., Coindreau, O., Beck, S., … Sevon, T. (2024). Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project. Annals of Nuclear Energy, 196, 110205 (14 pp.). https://doi.org/10.1016/j.anucene.2023.110205 |
| Minimal requirements to thermal-hydraulics/3D-neutron kinetics clustering for BWR transient analysis
Nikitin, K., Clifford, I., & Ferroukhi, H. (2024). Minimal requirements to thermal-hydraulics/3D-neutron kinetics clustering for BWR transient analysis. Annals of Nuclear Energy, 195, 110147 (12 pp.). https://doi.org/10.1016/j.anucene.2023.110147 |
| Choked-flow model parameter uncertainty determination using hierarchical calibration
Perret, G., Clifford, I. D., & Ferroukhi, H. (2024). Choked-flow model parameter uncertainty determination using hierarchical calibration. Annals of Nuclear Energy, 207, 110672 (12 pp.). https://doi.org/10.1016/j.anucene.2024.110672 |
| OFFBEAT V&V studies for REBEKA tests on cladding ballooning and burst during LOCA conditions
Verma, L., Clifford, I., Konarski, P., Scolaro, A., & Ferroukhi, H. (2024). OFFBEAT V&V studies for REBEKA tests on cladding ballooning and burst during LOCA conditions. Annals of Nuclear Energy, 208, 110773 (14 pp.). https://doi.org/10.1016/j.anucene.2024.110773 |
| Accelerated Monte Carlo perturbation calculation by surface recovery
Berry, L., Truchet, G., & Bonaccorsi, T. (2023). Accelerated Monte Carlo perturbation calculation by surface recovery. Annals of Nuclear Energy, 185, 109716 (11 pp.). https://doi.org/10.1016/j.anucene.2023.109716 |
| Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: first outcomes
Coindreau, O., Herranz, L. E., Bocanegra, R., Ederli, S., Maccari, P., Mascari, F., … Nudi, M. (2023). Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: first outcomes. Annals of Nuclear Energy, 188, 109796 (9 pp.). https://doi.org/10.1016/j.anucene.2023.109796 |
| Assessment of the influence of scaling on turbulent mixing in downcomer and core-inlet flow distribution
Fogliatto, E., Puragliesi, R., Clifford, I., & Ferroukhi, H. (2023). Assessment of the influence of scaling on turbulent mixing in downcomer and core-inlet flow distribution. Annals of Nuclear Energy, 185, 109715 (15 pp.). https://doi.org/10.1016/j.anucene.2023.109715 |
| Criticality assessments for long-term post-closure canister corrosion scenarios in a deep geological repository
Frankl, M., Wittel, M., Diomidis, N., Vasiliev, A., Ferroukhi, H., & Pudollek, S. (2023). Criticality assessments for long-term post-closure canister corrosion scenarios in a deep geological repository. Annals of Nuclear Energy, 180, 109449 (9 pp.). https://doi.org/10.1016/j.anucene.2022.109449 |
| Extension of the DYN3D/ATHLET code system to SFR applications: models description and initial validation
Fridman, E., Nikitin, E., Ponomarev, A., Di Nora, A., Kliem, S., & Mikityuk, K. (2023). Extension of the DYN3D/ATHLET code system to SFR applications: models description and initial validation. Annals of Nuclear Energy, 182, 109619 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109619 |
| Data-driven machine learning for disposal of high-level nuclear waste: a review
Hu, G., & Pfingsten, W. (2023). Data-driven machine learning for disposal of high-level nuclear waste: a review. Annals of Nuclear Energy, 180, 109452 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109452 |
| 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 |
| A hybrid domain overlapping method for coupling System Thermal Hydraulics and CFD codes
Huxford, A., Coppo Leite, V., Merzari, E., Zou, L., Petrov, V., & Manera, A. (2023). A hybrid domain overlapping method for coupling System Thermal Hydraulics and CFD codes. Annals of Nuclear Energy, 189, 109842 (11 pp.). https://doi.org/10.1016/j.anucene.2023.109842 |
| Addressing practical aspects of the nuclear criticality safety evaluations with frequentist statistics
Lee, H., Vasiliev, A., & Ferroukhi, H. (2023). Addressing practical aspects of the nuclear criticality safety evaluations with frequentist statistics. Annals of Nuclear Energy, 181, 109556 (17 pp.). https://doi.org/10.1016/j.anucene.2022.109556 |
