| 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 |
| Testing JENDL-5 data for U-235, Pu-239 and U-238 above the resolved resonance region
Pelloni, S., & Rochman, D. (2023). Testing JENDL-5 data for U-235, Pu-239 and U-238 above the resolved resonance region. Annals of Nuclear Energy, 182, 109603 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109603 |
| 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 |
| Non-destructive analysis of spent fuel samples using a gamma-blind fast neutron detector
Wolfertz, A., Perret, G., & Adams, R. (2023). Non-destructive analysis of spent fuel samples using a gamma-blind fast neutron detector. Annals of Nuclear Energy, 188, 109792 (10 pp.). https://doi.org/10.1016/j.anucene.2023.109792 |
| Uncertainty quantification study on gas phase iodine release from Fukushima Daiichi accident in unit 3
Kalilainen, J., & Lind, T. (2022). Uncertainty quantification study on gas phase iodine release from Fukushima Daiichi accident in unit 3. Annals of Nuclear Energy, 166, 108740 (13 pp.). https://doi.org/10.1016/j.anucene.2021.108740 |
| Unmoderated molten salt reactors design optimisation for power stability
Laureau, A., Bellè, A., Allibert, M., Heuer, D., Merle, E., & Pautz, A. (2022). Unmoderated molten salt reactors design optimisation for power stability. Annals of Nuclear Energy, 177, 109265 (8 pp.). https://doi.org/10.1016/j.anucene.2022.109265 |
| High accuracy measurement of the prompt neutron decay constant in CROCUS using gamma noise and bootstrapped uncertainties
Pakari, O. V., Lamirand, V., Mager, T., Frajtag, P., & Pautz, A. (2022). High accuracy measurement of the prompt neutron decay constant in CROCUS using gamma noise and bootstrapped uncertainties. Annals of Nuclear Energy, 170, 109011 (9 pp.). https://doi.org/10.1016/j.anucene.2022.109011 |
| Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data
Papadionysiou, M., Kim, S., Hursin, M., Vasiliev, A., Ferroukhi, H., Pautz, A., & Joo, H. G. (2022). Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data. Annals of Nuclear Energy, 178, 109385 (34 pp.). https://doi.org/10.1016/j.anucene.2022.109385 |
| Deep learning techniques for in-core perturbation identification and localization of time-series nuclear plant measurements
Papaoikonomou, A., Wingate, J., Verma, V., Durrant, A., Ioannou, G., Papagiannis, T., … Stafylopatis, A. (2022). Deep learning techniques for in-core perturbation identification and localization of time-series nuclear plant measurements. Annals of Nuclear Energy, 178, 109373 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109373 |
| Adjustment of JEFF-3.3 data for U-235 and Pu-239 in the fast, non-resonant energy range
Pelloni, S., & Rochman, D. (2022). Adjustment of JEFF-3.3 data for U-235 and Pu-239 in the fast, non-resonant energy range. Annals of Nuclear Energy, 177, 109296 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109296 |
| Development of a point-kinetics model in OpenFOAM, integration in GeN-Foam, and validation against FFTF experimental data
Radman, S., Fiorina, C., Song, P., & Pautz, A. (2022). Development of a point-kinetics model in OpenFOAM, integration in GeN-Foam, and validation against FFTF experimental data. Annals of Nuclear Energy, 168, 108891 (15 pp.). https://doi.org/10.1016/j.anucene.2021.108891 |
| Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5
Shama, A., Rochman, D., Caruso, S., & Pautz, A. (2022). Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5. Annals of Nuclear Energy, 165, 108758 (14 pp.). https://doi.org/10.1016/j.anucene.2021.108758 |
| Modelling and simulations of reactor neutron noise induced by mechanical vibrations
Vidal-Ferràndiz, A., Ginestar, D., Carreño, A., Verdú, G., Dokhane, A., Verma, V., … Vinai, P. (2022). Modelling and simulations of reactor neutron noise induced by mechanical vibrations. Annals of Nuclear Energy, 177, 109300 (21 pp.). https://doi.org/10.1016/j.anucene.2022.109300 |
| Analysis of diffusion coefficient correction methods applied for small-core, high-leakage reactors
Ványi, A. S., Hursin, M., & Czifrus, S. (2022). Analysis of diffusion coefficient correction methods applied for small-core, high-leakage reactors. Annals of Nuclear Energy, 174, 109147 (11 pp.). https://doi.org/10.1016/j.anucene.2022.109147 |
| Uncertainty analyses of neutron noise simulations in a Zero-Power reactor
Yum, S., Hursin, M., Vasiliev, A., Vinai, P., Mylonakis, A. G., Demazière, C., & Macián-Juan, R. (2022). Uncertainty analyses of neutron noise simulations in a Zero-Power reactor. Annals of Nuclear Energy, 174, 109157 (13 pp.). https://doi.org/10.1016/j.anucene.2022.109157 |
| Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing - part I: methodology demonstration
Di Nora, V. A., Fridman, E., Nikitin, E., Bilodid, Y., & Mikityuk, K. (2021). Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing - part I: methodology demonstration. Annals of Nuclear Energy, 155, 108183 (9 pp.). https://doi.org/10.1016/j.anucene.2021.108183 |
| Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing - part II: methodology application
Di Nora, V. A., Fridman, E., Nikitin, E., Bilodid, Y., & Mikityuk, K. (2021). Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing - part II: methodology application. Annals of Nuclear Energy, 163, 108541 (9 pp.). https://doi.org/10.1016/j.anucene.2021.108541 |
