ANGELUCCI, MICHELA Statistiche
ANGELUCCI, MICHELA
DIPARTIMENTO DI INGEGNERIA CIVILE E INDUSTRIALE
Sensitivity analysis in severe accident simulations:A historical perspective
2026-01-01 Angelucci, Michela; Cancemi, Salvatore A.; Paci, Sandro; Herranz, Luis E.
Advancing Pool Scrubbing Simulations: from Traditional to AI Methods
2025-01-01 Tinfena, G.; Angelucci, M.; Paci, S.; Herranz, L. E.
Corium Properties & Accident Scenarios: Preliminary Insights
2025-01-01 Mellace, B.; Angelucci, M.; Paci, S.; Herranz, L. E.
EFFECT OF CORIUM PROPERTIES’ UNCERTAINTIES ON A PWR SBO SEVERE ACCIDENT
2025-01-01 Mellace, B.; Angelucci, M.; Paci, S.; Herranz, L. E.
Fission Product Release Modeling in MELCOR: an Extension of the Validation
2025-01-01 Tinfena, G.; Angelucci, M.; Paci, S.; Herranz, L. E.
HPC modelling for nuclear safety assessment
2025-01-01 Cancemi, S A; Lo Frano, R; Angelucci, M; Pucciarelli, A; Subba, F; Wu, H
Hybrid neural network and statistical forecasting methodology for predictive monitoring and residual useful life estimation in nuclear power plant components
2025-01-01 Cancemi, S. A.; Angelucci, M.; Chierici, A.; Paci, S.; Lo Frano, R.
Inverse Uncertainty Quantification for Severe Accident Analyses
2025-01-01 Tinfena, G.; Angelucci, M.; Sargentini, L.; Paci, S.; Herranz, L. E.
Inverse uncertainty Quantification in the Severe accident Domain: Application to Fission Product release
2025-01-01 Tinfena, G.; Angelucci, M.; Sargentini, L.; Paci, S.; Herranz, L. E.
Phenomena Identification and Ranking Table for Containment Phenomena during Severe Accidents in Light Water Reactors
2025-01-01 Kljenak, Ivo; Angelucci, Michela; Paci, Sandro; Bentaib, Ahmed; Fernández-Cosials, Kevin; Jimenez, Gonzalo; Queral, Cesar; Di Giuli, Mirco; Yu, Shizhen; Herranz, Luis; Kelm, Stephan; Studer, Etienne
The Effect of Backfill Gas Pressure on the Thermal Response of a Dry Cask for Spent Nuclear Fuel
2025-01-01 Angelucci, Michela; Cancemi, Salvatore A.; LO FRANO, Rosa; Paci, Sandro
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
| Titolo | Data di pubblicazione | Autore(i) | File |
|---|---|---|---|
| Sensitivity analysis in severe accident simulations:A historical perspective | 1-gen-2026 | Angelucci, Michela; Cancemi, Salvatore A.; Paci, Sandro; Herranz, Luis E. | |
| Advancing Pool Scrubbing Simulations: from Traditional to AI Methods | 1-gen-2025 | Tinfena, G.; Angelucci, M.; Paci, S.; Herranz, L. E. | |
| Corium Properties & Accident Scenarios: Preliminary Insights | 1-gen-2025 | Mellace, B.; Angelucci, M.; Paci, S.; Herranz, L. E. | |
| EFFECT OF CORIUM PROPERTIES’ UNCERTAINTIES ON A PWR SBO SEVERE ACCIDENT | 1-gen-2025 | Mellace, B.; Angelucci, M.; Paci, S.; Herranz, L. E. | |
| Fission Product Release Modeling in MELCOR: an Extension of the Validation | 1-gen-2025 | Tinfena, G.; Angelucci, M.; Paci, S.; Herranz, L. E. | |
| HPC modelling for nuclear safety assessment | 1-gen-2025 | Cancemi, S A; Lo Frano, R; Angelucci, M; Pucciarelli, A; Subba, F; Wu, H | |
| Hybrid neural network and statistical forecasting methodology for predictive monitoring and residual useful life estimation in nuclear power plant components | 1-gen-2025 | Cancemi, S. A.; Angelucci, M.; Chierici, A.; Paci, S.; Lo Frano, R. | |
| Inverse Uncertainty Quantification for Severe Accident Analyses | 1-gen-2025 | Tinfena, G.; Angelucci, M.; Sargentini, L.; Paci, S.; Herranz, L. E. | |
| Inverse uncertainty Quantification in the Severe accident Domain: Application to Fission Product release | 1-gen-2025 | Tinfena, G.; Angelucci, M.; Sargentini, L.; Paci, S.; Herranz, L. E. | |
| Phenomena Identification and Ranking Table for Containment Phenomena during Severe Accidents in Light Water Reactors | 1-gen-2025 | Kljenak, Ivo; Angelucci, Michela; Paci, Sandro; Bentaib, Ahmed; Fernández-Cosials, Kevin; Jimenez, Gonzalo; Queral, Cesar; Di Giuli, Mirco; Yu, Shizhen; Herranz, Luis; Kelm, Stephan; Studer, Etienne | |
| The Effect of Backfill Gas Pressure on the Thermal Response of a Dry Cask for Spent Nuclear Fuel | 1-gen-2025 | Angelucci, Michela; Cancemi, Salvatore A.; LO FRANO, Rosa; Paci, Sandro | |
| 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 |