Matteo D'Onorio | Ricerc@Sapienza

Pubblicazioni

Titolo	Pubblicato in	Anno
Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package	ANNALS OF NUCLEAR ENERGY	2025
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project	ANNALS OF NUCLEAR ENERGY	2024
Nuclear safety Enhanced: A Deep dive into current and future RAVEN applications	NUCLEAR ENGINEERING AND DESIGN	2024
Experimental insights on iron-based alloys corrosion in water cooled loops	NUCLEAR MATERIALS AND ENERGY	2024
Development of a thermal-hydraulic model for the EU-DEMO Tokamak building and LOCA simulation	ENERGIES	2023
Design and integration of the EU-DEMO water-cooled lead lithium breeding blanket	ENERGIES	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	2023
Water Chemistry Impact on Activated Corrosion Products: An Assessment on Tokamak Reactors	ENERGIES	2023
Thermal-hydraulic optimization of a proposed EU-DEMO hydrogen passive removal system	FUSION ENGINEERING AND DESIGN	2023
Passive hydrogen recombination during a beyond design basis accident in a fusion DEMO plant	ENERGIES	2023
Dynamic event tree analysis of a severe accident sequence in a boiling water reactor experiencing a cyberattack scenario	ANNALS OF NUCLEAR ENERGY	2023
Tritium transport in the vacuum vessel pressure suppression system for helium cooled pebble bed	FUSION ENGINEERING AND DESIGN	2023
Cutting-edge R&D activities of CIRTEN in support of the Technology Park annexed to the Italian National Repository of radioactive waste	IL NUOVO CIMENTO C	2023
DEMO – The main achievements of the Pre – Concept phase of the safety and environmental work package and the development of the GSSR	FUSION ENGINEERING AND DESIGN	2022
Dynamic event tree analysis as a tool for risk assessment in nuclear fusion plants using RAVEN and MELCOR	IEEE TRANSACTIONS ON PLASMA SCIENCE	2022
Analysis of Fukushima Daiichi unit 4 spent fuel pool using MELCOR	JOURNAL OF PHYSICS. CONFERENCE SERIES	2022
Severe accident sensitivity and uncertainty estimation using MELCOR and RAVEN	JOURNAL OF PHYSICS. CONFERENCE SERIES	2022
RAVEN/OSCAR-Fusion coupling for activated corrosion products assessments, sensitivity, and uncertainty quantification	IEEE TRANSACTIONS ON PLASMA SCIENCE	2022
Transient analysis of a locked rotor/shaft seizure accident involving the EU-DEMO WCLL Breeding Blanket primary cooling circuits	FUSION ENGINEERING AND DESIGN	2022
DEMO divertor cassette and plasma facing unit in vessel loss-of-coolant accident	ENERGIES	2022

Progetti di Ricerca

Development of an innovative tool to perform a dynamic probabilistic risk assessment of nuclear power plants.

Gruppi di ricerca

NERG - Nuclear Engineering Research Group