ANGELUCCI, MICHELA Statistiche
ANGELUCCI, MICHELA
DIPARTIMENTO DI INGEGNERIA CIVILE E INDUSTRIALE
Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package
2025-01-01 Brumm, S.; Gabrielli, F.; Sanchez Espinoza, V.; Stakhanova, A.; Groudev, P.; Petrova, P.; Vryashkova, P.; Ou, P.; Zhang, W.; Malkhasyan, A.; Herranz, L. E.; Iglesias Ferrer, R.; Angelucci, M.; Berdai, M.; Mascari, F.; Agnello, G.; Sevbo, O.; Iskra, A.; Martinez Quiroga, V.; Nudi, M.; Hoefer, A.; Pauli, E. -M.; Beck, S.; Tiborcz, L.; Coindreau, O.; Clark, G.; Lamont, I.; Zheng, X.; Kubo, K.; Lee, B.; Valincius, M.; Malicki, M.; Lind, T.; Vorobyov, Y.; Kotsuba, O.; Di Giuli, M.; Ivanov, I.; D'Onorio, M.; Giannetti, F.; Sevon, T.
ANALYSIS OF THE DYNAMIC BEHAVIOUR OF A NUCLEAR CONTAINMENT STRUCTURE UNDER MISSILE IMPACT
2024-01-01 Lo Frano, R; Cancemi, S. A.; Angelucci, M.; Pugliese, G.
Application of Inverse Uncertainty Quantification in the Severe Accident Domain: Fission Product Release Modelling
2024-01-01 Tinfena, G.; Angelucci, M.; Sargentini, L.; Paci, S.; Herranz, L. E.
APPLICATION OF SENSITIVITY ANALYSIS TECHNIQUES TO A LOW DIMENTIONAL PROBLEM IN THE FRAME OF SEVERE ACCIDENTS
2024-01-01 Angelucci, M.; Paci, S.; Cancemi, S. A.; Lo Frano, R.
CROSS-COMPARISON OF DIFFERENT TECHNIQUES FOR SENSITIVITY ANALYSIS IN SEVERE ACCIDENTS: APPLICATION TO A SBO IN A PWR
2024-01-01 Angelucci, M.; Herranz, L. E.; Paci, S.
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project
2024-01-01 Mascari, F.; Bersano, A.; Massone, M.; Agnello, G.; Coindreau, O.; Beck, S.; Tiborcz, L.; Paci, S.; Angelucci, M.; Herranz, L. E.; Bocanegra, R.; Pontillon, Y.; Berdai, M.; Cherednichenko, O.; Iskra, A.; Nudi, M.; Groudev, P.; Petrova, P.; Kretzschmar, F.; Gabrielli, F.; Kanglong, Z.; Vileiniškis, V.; Kaliatka, T.; Kalilainen, J.; Malicki, M.; Gumenyuk, D.; Vorobyov, Y.; Kotsuba, O.; Dejardin, P.; Di Giuli, M.; Thomas, R.; Ivanov, I. V.; Giannetti, F.; D'Onorio, M.; Caruso, G.; Salay, M.; Sevon, T.
MELCOR – DAKOTA coupling for uncertainty analyses in the SNAP environment/architecture
2024-01-01 Mascari, F.; Bersano, A.; Agnello, G.; Angelucci, M.; Phillips, J.; Luxat, D.
NEURAL NETWORK-DRIVEN METHODOLOGY FOR PREDICTIVE HEALTH MONITORING AND AGING MANAGEMENT IN NUCLEAR POWER PLANT OPERATIONS
2024-01-01 Cancemi, S. A.; Angelucci, M.; Lo Frano, R.; Paci, S.
On the behavior of a concrete-based dry cask for spent nuclear fuel in off-normal and accidental conditions
2024-01-01 Angelucci, Michela; Herranz, Luis E.; Paci, Sandro
SOURCE TERM UNCERTAINTIES IN UNMITIGATED SBO SEQUENCES IN A PWR-1000: INSIGHTS FROM THE EU-MUSA PROJECT
2024-01-01 Iglesias, R.; Angelucci, M.; Paci, S.; Herranz, L. E.
Surrogate Modeling Advancements in Nuclear Fuel Engineering: Bridging the Gap Between Accuracy and Efficiency
2024-01-01 Cancemi, S. A.; Angelucci, M.; Lo Frano, R.; Paci, S.
Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part I: sensitivity studies
2024-01-01 Angelucci, M.; Paci, S.
Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part II: application
2024-01-01 Angelucci, M.; Paci, S.
UNCERTAINTIES ON FISSION PRODUCT RELEASE IN A LOSS-OF-COOLING SCENARIO IN A SPENT FUEL POOL WITH MELCOR 2.0
2024-01-01 Garcia, M.; Herranz, L. E.; Angelucci, M.; Paci, S.
Assessment of Uncertainties Effect on Accident Progression and Fission Product Release in a Spent Fuel Pool
2023-01-01 Garcia, Monica; Angelucci, Michela; Paci, Sandro; Herranz, Luis E.
Current status of MELCOR 2.2 for fusion safety analyses
2023-01-01 Mascari, F.; Bersano, A.; Adorni, M.; D'Ovidio, G.; Martín-Fuertes, F.; Jin, X. Z.; Mazzini, G.; Gonfiotti, B.; Georgiev, G.; Leskovar, M.; Bertani, C.; Testoni, R.; Giannetti, F.; D'Onorio, M.; Agnello, G.; Di Maio, P. A.; Angelucci, M.; Paci, S.; Grippo, G.; Fernández-Cosials, K.; Dongiovanni, D.; Malicki, M.
Preliminary uncertainty assessment of the containment behavior for the Phebus FPT1 test
2023-01-01 Angelucci, Michela; Paci, Sandro
Uncertainty and Sensitivity Analyses of Source Term Estimates during an Unmitigated SBO Sequence in a PWR-1000 Reactor
2023-01-01 Iglesias, Rafael; Angelucci, Michela; Paci, Sandro; Herranz, Luis E.
Best-estimate for system codes (Besyc): A new software to perform best-estimate plus uncertainty analyses with thermal-hydraulic and safety system codes for both fusion and fission scenarios
2022-01-01 Gonfiotti, B.; Angelucci, M.; Ghidersa, B. -E.; Jin, X. Z.; Ionescu-Bujor, M.; Paci, S.; Stieglitz, R.
CIEMAT's Lessons learned and insights from PHEBUS-FPT1 analysis
2022-01-01 Bocanegra, R.; Herranz, Luis E.; Angelucci, M.; Paci, S.
| Titolo | Data di pubblicazione | Autore(i) | File |
|---|---|---|---|
| Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package | 1-gen-2025 | Brumm, S.; Gabrielli, F.; Sanchez Espinoza, V.; Stakhanova, A.; Groudev, P.; Petrova, P.; Vryashkova, P.; Ou, P.; Zhang, W.; Malkhasyan, A.; Herranz, L. E.; Iglesias Ferrer, R.; Angelucci, M.; Berdai, M.; Mascari, F.; Agnello, G.; Sevbo, O.; Iskra, A.; Martinez Quiroga, V.; Nudi, M.; Hoefer, A.; Pauli, E. -M.; Beck, S.; Tiborcz, L.; Coindreau, O.; Clark, G.; Lamont, I.; Zheng, X.; Kubo, K.; Lee, B.; Valincius, M.; Malicki, M.; Lind, T.; Vorobyov, Y.; Kotsuba, O.; Di Giuli, M.; Ivanov, I.; D'Onorio, M.; Giannetti, F.; Sevon, T. | |
| ANALYSIS OF THE DYNAMIC BEHAVIOUR OF A NUCLEAR CONTAINMENT STRUCTURE UNDER MISSILE IMPACT | 1-gen-2024 | Lo Frano, R; Cancemi, S. A.; Angelucci, M.; Pugliese, G. | |
| Application of Inverse Uncertainty Quantification in the Severe Accident Domain: Fission Product Release Modelling | 1-gen-2024 | Tinfena, G.; Angelucci, M.; Sargentini, L.; Paci, S.; Herranz, L. E. | |
| APPLICATION OF SENSITIVITY ANALYSIS TECHNIQUES TO A LOW DIMENTIONAL PROBLEM IN THE FRAME OF SEVERE ACCIDENTS | 1-gen-2024 | Angelucci, M.; Paci, S.; Cancemi, S. A.; Lo Frano, R. | |
| CROSS-COMPARISON OF DIFFERENT TECHNIQUES FOR SENSITIVITY ANALYSIS IN SEVERE ACCIDENTS: APPLICATION TO A SBO IN A PWR | 1-gen-2024 | Angelucci, M.; Herranz, L. E.; Paci, S. | |
| Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project | 1-gen-2024 | Mascari, F.; Bersano, A.; Massone, M.; Agnello, G.; Coindreau, O.; Beck, S.; Tiborcz, L.; Paci, S.; Angelucci, M.; Herranz, L. E.; Bocanegra, R.; Pontillon, Y.; Berdai, M.; Cherednichenko, O.; Iskra, A.; Nudi, M.; Groudev, P.; Petrova, P.; Kretzschmar, F.; Gabrielli, F.; Kanglong, Z.; Vileiniškis, V.; Kaliatka, T.; Kalilainen, J.; Malicki, M.; Gumenyuk, D.; Vorobyov, Y.; Kotsuba, O.; Dejardin, P.; Di Giuli, M.; Thomas, R.; Ivanov, I. V.; Giannetti, F.; D'Onorio, M.; Caruso, G.; Salay, M.; Sevon, T. | |
| MELCOR – DAKOTA coupling for uncertainty analyses in the SNAP environment/architecture | 1-gen-2024 | Mascari, F.; Bersano, A.; Agnello, G.; Angelucci, M.; Phillips, J.; Luxat, D. | |
| NEURAL NETWORK-DRIVEN METHODOLOGY FOR PREDICTIVE HEALTH MONITORING AND AGING MANAGEMENT IN NUCLEAR POWER PLANT OPERATIONS | 1-gen-2024 | Cancemi, S. A.; Angelucci, M.; Lo Frano, R.; Paci, S. | |
| On the behavior of a concrete-based dry cask for spent nuclear fuel in off-normal and accidental conditions | 1-gen-2024 | Angelucci, Michela; Herranz, Luis E.; Paci, Sandro | |
| SOURCE TERM UNCERTAINTIES IN UNMITIGATED SBO SEQUENCES IN A PWR-1000: INSIGHTS FROM THE EU-MUSA PROJECT | 1-gen-2024 | Iglesias, R.; Angelucci, M.; Paci, S.; Herranz, L. E. | |
| Surrogate Modeling Advancements in Nuclear Fuel Engineering: Bridging the Gap Between Accuracy and Efficiency | 1-gen-2024 | Cancemi, S. A.; Angelucci, M.; Lo Frano, R.; Paci, S. | |
| Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part I: sensitivity studies | 1-gen-2024 | Angelucci, M.; Paci, S. | |
| Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part II: application | 1-gen-2024 | Angelucci, M.; Paci, S. | |
| UNCERTAINTIES ON FISSION PRODUCT RELEASE IN A LOSS-OF-COOLING SCENARIO IN A SPENT FUEL POOL WITH MELCOR 2.0 | 1-gen-2024 | Garcia, M.; Herranz, L. E.; Angelucci, M.; Paci, S. | |
| Assessment of Uncertainties Effect on Accident Progression and Fission Product Release in a Spent Fuel Pool | 1-gen-2023 | Garcia, Monica; Angelucci, Michela; Paci, Sandro; Herranz, Luis E. | |
| Current status of MELCOR 2.2 for fusion safety analyses | 1-gen-2023 | Mascari, F.; Bersano, A.; Adorni, M.; D'Ovidio, G.; Martín-Fuertes, F.; Jin, X. Z.; Mazzini, G.; Gonfiotti, B.; Georgiev, G.; Leskovar, M.; Bertani, C.; Testoni, R.; Giannetti, F.; D'Onorio, M.; Agnello, G.; Di Maio, P. A.; Angelucci, M.; Paci, S.; Grippo, G.; Fernández-Cosials, K.; Dongiovanni, D.; Malicki, M. | |
| Preliminary uncertainty assessment of the containment behavior for the Phebus FPT1 test | 1-gen-2023 | Angelucci, Michela; Paci, Sandro | |
| Uncertainty and Sensitivity Analyses of Source Term Estimates during an Unmitigated SBO Sequence in a PWR-1000 Reactor | 1-gen-2023 | Iglesias, Rafael; Angelucci, Michela; Paci, Sandro; Herranz, Luis E. | |
| Best-estimate for system codes (Besyc): A new software to perform best-estimate plus uncertainty analyses with thermal-hydraulic and safety system codes for both fusion and fission scenarios | 1-gen-2022 | Gonfiotti, B.; Angelucci, M.; Ghidersa, B. -E.; Jin, X. Z.; Ionescu-Bujor, M.; Paci, S.; Stieglitz, R. | |
| CIEMAT's Lessons learned and insights from PHEBUS-FPT1 analysis | 1-gen-2022 | Bocanegra, R.; Herranz, Luis E.; Angelucci, M.; Paci, S. |