| Analyses of jet buoyant flow in a multicompartment containment using an open-source solver
Chae, M. S., Lee, J., Cho, H. K., Kelm, S., & Paladino, D. (2024). Analyses of jet buoyant flow in a multicompartment containment using an open-source solver. Nuclear Technology. https://doi.org/10.1080/00295450.2024.2362527 |
| P2M simulation exercise on past fuel melting irradiation experiments
D’Ambrosi, V., Sercombe, J., Bejaoui, S., Chaieb, A., Baurens, B., Largenton, R., … Peltonen, J. (2024). P2M simulation exercise on past fuel melting irradiation experiments. Nuclear Technology, 210(2), 189-2015. https://doi.org/10.1080/00295450.2023.2194270 |
| Validation of a hybrid domain overlapping coupling between SAM and CFD against the TALL-3D transients
Huxford, A., Zou, L., Hu, R., Petrov, V., & Manera, A. (2024). Validation of a hybrid domain overlapping coupling between SAM and CFD against the TALL-3D transients. Nuclear Technology. https://doi.org/10.1080/00295450.2024.2352665 |
| High-fidelity velocity and concentration measurements of turbulent Buoyant Jets
Valori, V., Qin, S., Petrov, V., & Manera, A. (2024). High-fidelity velocity and concentration measurements of turbulent Buoyant Jets. Nuclear Technology. https://doi.org/10.1080/00295450.2024.2355406 |
| Recent developments and findings of heat pipe experiments for microreactor applications
Yilgor, I., Sellers, Z. D., Hartvigsen, J. L., Sweetland, K. M., Huang, P. H., Ahn, T., … Sabharwall, P. (2024). Recent developments and findings of heat pipe experiments for microreactor applications. Nuclear Technology. https://doi.org/10.1080/00295450.2024.2375488 |
| Measurement of local void fraction of air water flow in the 8 × 8 rod bundle using high-resolution gamma-ray tomography
Ahn, T., Diaz, J., Adams, R., Petrov, V., & Manera, A. (2023). Measurement of local void fraction of air water flow in the 8 × 8 rod bundle using high-resolution gamma-ray tomography. Nuclear Technology, 209, 1898-1913. https://doi.org/10.1080/00295450.2023.2197680 |
| High-fidelity modeling and experiments to inform safety analysis codes for heat pipe microreactors
Bourdot Dutra, C. da S., Merzari, E., Acierno, J., Kraus, A., Manera, A., Petrov, V., … Shaver, D. (2023). High-fidelity modeling and experiments to inform safety analysis codes for heat pipe microreactors. Nuclear Technology, 209, 1592-1616. https://doi.org/10.1080/00295450.2023.2181040 |
| High-resolution X-Ray radiography methods developed for Post-CHF experiment
Diaz, J., Liu, Q., Petrov, V., Manera, A., & Sun, X. (2023). High-resolution X-Ray radiography methods developed for Post-CHF experiment. Nuclear Technology, 209(10), 1442-1465. https://doi.org/10.1080/00295450.2022.2133504 |
| On the development of a novel acoustic flowmeter for high-temperature gas-cooled reactors
Mao, J., Petrov, V., Manera, A., Howard, T. K., & Cetiner, S. M. (2023). On the development of a novel acoustic flowmeter for high-temperature gas-cooled reactors. Nuclear Technology, 209(10). https://doi.org/10.1080/00295450.2022.2133505 |
| An experimental and theoretical examination of air ingress rates during small- and medium-break air ingress accidents
Welker, Z., Manera, A., Petrov, V., & Balestra, P. (2023). An experimental and theoretical examination of air ingress rates during small- and medium-break air ingress accidents. Nuclear Technology, 209(10), 1577-1591. https://doi.org/10.1080/00295450.2022.2134673 |
| Global sensitivity analysis and bayesian calibration on a series of reflood experiments with varying boundary conditions
Perret, G., Wicaksono, D., Clifford, I. D., & Ferroukhi, H. (2022). Global sensitivity analysis and bayesian calibration on a series of reflood experiments with varying boundary conditions. Nuclear Technology, 208(4), 711-722. https://doi.org/10.1080/00295450.2021.1936879 |
| Interface tracking investigation of the sliding bubbles effects on heat transfer in the laminar regime
Wong, K. W., Bures, L., & Mikityuk, K. (2022). Interface tracking investigation of the sliding bubbles effects on heat transfer in the laminar regime. Nuclear Technology, 208(8), 1266-1278. https://doi.org/10.1080/00295450.2021.1971025 |
| The PyNE-based burnup analysis method for accelerator-driven subcritical systems
Li, J. Y., Gu, L., Xu, H. S., Dai, Y., Zhang, Y. P., Yao, C. F., … Yang, S. (2021). The PyNE-based burnup analysis method for accelerator-driven subcritical systems. Nuclear Technology, 207(2), 270-284. https://doi.org/10.1080/00295450.2020.1757963 |
| Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2020). Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques. Nuclear Technology, 206(10), 1566-1583. https://doi.org/10.1080/00295450.2019.1701906 |
| Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project
Pellegrini, M., Herranz, L., Sonnenkalb, M., Lind, T., Maruyama, Y., Gauntt, R., … Mizokami, S. (2020). Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project. Nuclear Technology, 206(9), 1449-1463. https://doi.org/10.1080/00295450.2020.1724731 |
| Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code
Papini, D., Andreani, M., Steiner, P., Ničeno, B., Klügel, J. U., & Prasser, H. M. (2019). Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code. Nuclear Technology, 205(1-2), 153-173. https://doi.org/10.1080/00295450.2018.1505356 |
| Global sensitivity and registration strategy for temperature profile of reflood experiment simulations
Perret, G., Wicaksono, D., Clifford, I. D., & Ferroukhi, H. (2019). Global sensitivity and registration strategy for temperature profile of reflood experiment simulations. Nuclear Technology, 205(12), 1638-1651. https://doi.org/10.1080/00295450.2019.1591154 |
| Unsteady single-phase natural-circulation flow mixing prediction using 3-D thermal-hydraulic system and CFD Codes
Bousbia Salah, A., Ceuca, S. C., Puragliesi, R., Mukin, R., Grahn, A., Kliem, S., … Austregesilo, H. (2018). Unsteady single-phase natural-circulation flow mixing prediction using 3-D thermal-hydraulic system and CFD Codes. Nuclear Technology, 203(3), 293-314. https://doi.org/10.1080/00295450.2018.1461517 |
| Modeling of aerosol fission product scrubbing in experiments and in integral severe accident scenarios
Rýdl, A., Fernandez-Moguel, L., & Lind, T. (2018). Modeling of aerosol fission product scrubbing in experiments and in integral severe accident scenarios. Nuclear Technology, 205(5), 655-670. https://doi.org/10.1080/00295450.2018.1511213 |
| Towards a consolidated approach for the assessment of evaluation models of nuclear power reactors
Epiney, A., Canepa, S., Zerkak, O., & Ferroukhi, H. (2016). Towards a consolidated approach for the assessment of evaluation models of nuclear power reactors. Nuclear Technology, 196(2), 223-237. https://doi.org/10.13182/NT16-47 |
