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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).
Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5
Park, J., Kim, W., Hursin, M., Perret, G., Vasiliev, A., Rochman, D., … Lee, D. (2019). Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5. Annals of Nuclear Energy, 131, 9-22. https://doi.org/10.1016/j.anucene.2019.03.023
Analyses of the SPERT-III RIA experiments with nuclear data uncertainty quantification using three different covariance matrix libraries
Dokhane, A., Vasiliev, A., Rochman, D., Ferroukhi, H., & Grandi, G. (2018). Analyses of the SPERT-III RIA experiments with nuclear data uncertainty quantification using three different covariance matrix libraries. In Proceedings of the PHYTRA4 conference (pp. 91-102). American Nuclear Society (ANS).
Validation of PSI best estimate plus uncertainty methodology against SPERT-III reactivity initiated accident experiments
Dokhane, A., Grandi, G., Vasiliev, A., Rochman, D., & Ferroukhi, H. (2018). Validation of PSI best estimate plus uncertainty methodology against SPERT-III reactivity initiated accident experiments. Annals of Nuclear Energy, 118, 178-184. https://doi.org/10.1016/j.anucene.2018.04.022
Convergence analysis and criterion for data assimilation with sensitivities from Monte Carlo neutron transport codes
Siefman, D., Hursin, M., Aufiero, M., Bidaud, A., & Pautz, A. (2018). Convergence analysis and criterion for data assimilation with sensitivities from Monte Carlo neutron transport codes. In Proceedings of the PHYSOR 2018 (p. (10 pp.). American Nuclear Society.
Validation of SIMULATE-3K against SPERT-III RIA experiments with quantification of nuclear data uncertainties
Dokhane, A., Leray, O., Rochman, D., Ferroukhi, H., Pautz, A., & Grandi, G. (2016). Validation of SIMULATE-3K against SPERT-III RIA experiments with quantification of nuclear data uncertainties. In Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century (pp. 3803-3812). American Nuclear Society.
Evaluation of deterministic sampling for uncertainty quantification in a probabilistic accident analysis model
Rahman, S., Karanki, D. R., Wicaksono, D., Zerkak, O., & Dang, V. N. (2016). Evaluation of deterministic sampling for uncertainty quantification in a probabilistic accident analysis model (p. N11P0291 (15 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). .
Bayesian calibration of thermal-hydraulics model with time-dependent output
Wicaksono, D., Zerkak, O., & Pautz, A. (2016). Bayesian calibration of thermal-hydraulics model with time-dependent output (p. N11P0491 (14 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). .
Advanced calculation methodology for manufacturing and technological parameters' uncertainties propagation at arbitrary level of lattice elements grouping
Pecchia, M., Vasiliev, A., Leray, O., Ferroukhi, H., & Pautz, A. (2015). Advanced calculation methodology for manufacturing and technological parameters' uncertainties propagation at arbitrary level of lattice elements grouping. Journal of Nuclear Science and Technology, 52(7-8), 1084-1092. https://doi.org/10.1080/00223131.2015.1032382