| Lasso Monte Carlo, a variation on multi fidelity methods for high-dimensional uncertainty quantification
Albà, A., Boiger, R., Rochman, D., & Adelmann, A. (2025). Lasso Monte Carlo, a variation on multi fidelity methods for high-dimensional uncertainty quantification. Journal of Applied Statistics, 1-37. https://doi.org/10.1080/02664763.2025.2487505 |
| Uncertainty quantification of spent nuclear fuel with multifidelity Monte Carlo
Albà, A., Adelmann, A., & Rochman, D. (2025). Uncertainty quantification of spent nuclear fuel with multifidelity Monte Carlo. Annals of Nuclear Energy, 211, 110892 (17 pp.). https://doi.org/10.1016/j.anucene.2024.110892 |
| Uncertainty quantification for severe-accident reactor modelling: results and conclusions of the MUSA reactor applications work package
Brumm, S., Gabrielli, F., Sanchez Espinoza, V., Stakhanova, A., Groudev, P., Petrova, P., … Sevon, T. (2025). Uncertainty quantification for severe-accident reactor modelling: results and conclusions of the MUSA reactor applications work package. Annals of Nuclear Energy, 211, 110962 (16 pp.). https://doi.org/10.1016/j.anucene.2024.110962 |
| 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 |
| Uncertainty quantification on spent nuclear fuel with LMC
Albà, A., Adelmann, A., & Rochman, D. (2024). Uncertainty quantification on spent nuclear fuel with LMC. In K. Suyama, S. Gunji, T. Watanabe, S. Araki, K. Fukuda, K. Shimada, … H. H. Nguyen (Eds.), Proceedings of the 12th international conference on nuclear criticality safety (pp. 1-10). Japan Atomic Energy Agency. |
| Stability and bifurcation analysis of Oskarshamn-2 event with nuclear data and kinetic parameter uncertainties
Dokhane, A., Vasiliev, A., & Ferroukhi, H. (2024). Stability and bifurcation analysis of Oskarshamn-2 event with nuclear data and kinetic parameter uncertainties. Nuclear Engineering and Design, 430, 113678 (11 pp.). https://doi.org/10.1016/j.nucengdes.2024.113678 |
| 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 |
| Nuclear data effect on BWR stability parameter uncertainty at stable core conditions
Dokhane, A., Vasiliev, A., Hursin, M., & Ferroukhi, H. (2023). Nuclear data effect on BWR stability parameter uncertainty at stable core conditions. Nuclear Engineering and Design, 414, 112620 (9 pp.). https://doi.org/10.1016/j.nucengdes.2023.112620 |
| Uncertainty quantification of a light water pulsed-neutron die-away experiment to thermal neutron scattering laws
Siefman, D., Hursin, M., Percher, C., & Heinrichs, D. (2023). Uncertainty quantification of a light water pulsed-neutron die-away experiment to thermal neutron scattering laws. Nuclear Science and Engineering, 197, 14-24. https://doi.org/10.1080/00295639.2022.2103344 |
| A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments
Dokhane, A., Vasiliev, A., Hursin, M., Rochman, D., & Ferroukhi, H. (2022). A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments. Nuclear Engineering and Technology, 54(5), 1804-1812. https://doi.org/10.1016/j.net.2021.10.042 |
| 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 |
| 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 |
| Quantitative assessment of uncertainties and sensitivities in the estimation of life loss due to the instantaneous break of a hypothetical dam in Switzerland
Kalinina, A., Spada, M., & Burgherr, P. (2021). Quantitative assessment of uncertainties and sensitivities in the estimation of life loss due to the instantaneous break of a hypothetical dam in Switzerland. Water, 13(23), 3414 (22 pp.). https://doi.org/10.3390/w13233414 |
| Uncertainty and sensitivity analysis of the chemistry of cesium sorption in deep geological repositories
Ayoub, A., Pfingsten, W., Podofillini, L., & Sansavini, G. (2020). Uncertainty and sensitivity analysis of the chemistry of cesium sorption in deep geological repositories. Applied Geochemistry, 117, 104607 (12 pp.). https://doi.org/10.1016/j.apgeochem.2020.104607 |
| Artificial neural networks as surrogate models for uncertainty quantification and data assimilation in 2-D/3-D fuel performance studies
Fiorina, C., Scolaro, A., Siefman, D., Hursin, M., & Pautz, A. (2020). Artificial neural networks as surrogate models for uncertainty quantification and data assimilation in 2-D/3-D fuel performance studies. Journal of Nuclear Engineering, 1(1), 54-62. https://doi.org/10.3390/jne1010005 |
| Treatment of the implicit effect in Shark-X
Hursin, M., Pelloni, S., Vasiliev, A., & Ferroukhi, H. (2020). Treatment of the implicit effect in Shark-X. Annals of Nuclear Energy, 138, 107178 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107178 |
| Metamodeling for uncertainty quantification of a flood wave model for concrete dam breaks
Kalinina, A., Spada, M., Vetsch, D., Marelli, S., Whealton, C., Burgherr, P., & Sudret, B. (2020). Metamodeling for uncertainty quantification of a flood wave model for concrete dam breaks. Energies, 13(14), 3685 (25 pp.). https://doi.org/10.3390/en13143685 |
| Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor
Kim, W., Hursin, M., Pautz, A., Vincent, L., Pavel, F., & Lee, D. (2020). Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor. Annals of Nuclear Energy, 136, 107034 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107034 |
| Uncertainty quantification analysis and optimization for proton therapy beam lines
Rizzoglio, V., Adelmann, A., Gerbershagen, A., Meer, D., Nesteruk, K. P., & Schippers, J. M. (2020). Uncertainty quantification analysis and optimization for proton therapy beam lines. Physica Medica, 75, 11-18. https://doi.org/10.1016/j.ejmp.2020.05.013 |
| Uncertainty quantification of LWR-proteus phase II experiments using CASMO-5
Hursin, M., Park, J., Kim, W., Siefman, D., Perret, G., Vasiliev, A., … Lee, D. (2019). Uncertainty quantification of LWR-proteus phase II experiments using CASMO-5. In International conference on mathematics computational methods applied to nuclear science and engineering (M&C 2019) (p. (9 pp.). American Nuclear Society (ANS). |
