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View article: Hybrid neural network and statistical forecasting methodology for predictive monitoring and residual useful life estimation in nuclear power plant components
Hybrid neural network and statistical forecasting methodology for predictive monitoring and residual useful life estimation in nuclear power plant components Open
View article: Major Achievements of the EC MUSA Project
Major Achievements of the EC MUSA Project Open
The maturity of severe accident (SA) codes, progress in computational methods, and computer infrastructures were considered a sound platform for conducting, for the first time in SA modeling, a systematic and broad application of uncertain…
View article: The Effect of Backfill Gas Pressure on the Thermal Response of a Dry Cask for Spent Nuclear Fuel
The Effect of Backfill Gas Pressure on the Thermal Response of a Dry Cask for Spent Nuclear Fuel Open
Dry systems are being employed worldwide as interim storage for Spent Nuclear Fuel (SNF). Despite not being designed as permanent repositories, the safe storage of SNF must still be ensured. In this framework, few experimental campaigns ha…
View article: ERMSAR 2024 conference “European Review Meeting on Severe Accident Research”
ERMSAR 2024 conference “European Review Meeting on Severe Accident Research” Open
View article: On the behavior of a concrete-based dry cask for spent nuclear fuel in off-normal and accidental conditions
On the behavior of a concrete-based dry cask for spent nuclear fuel in off-normal and accidental conditions Open
The safe storage of Spent Nuclear Fuel (SNF) within a dry cask system must be guaranteed for any operating condition. In particular, the Peak Cladding Temperature (PCT) is currently employed as a measure of the fuel integrity in normal con…
View article: Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part I: sensitivity studies.
Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part I: sensitivity studies. Open
The United States (US) Department Of Energy (DOE) has addressed the thermal analysis of the Spent Nuclear Fuel (SNF) stored within a dry cask system as a matter of high priority. In this regard, it is of utmost importance that simulation t…
View article: Hybrid Neural Network and Statistical Forecasting Methodology for Predictive Health Monitoring and Residual Useful Life Estimation in Nuclear Power Plant Components
Hybrid Neural Network and Statistical Forecasting Methodology for Predictive Health Monitoring and Residual Useful Life Estimation in Nuclear Power Plant Components Open
View article: Corrigendum: Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part I: sensitivity studies. (2024 J. Phys.: Conf. Ser. 2685 012043)
Corrigendum: Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part I: sensitivity studies. (2024 J. Phys.: Conf. Ser. 2685 012043) Open
Please see Article PDF for corrigendum text.
View article: Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part II: application.
Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part II: application. Open
Nowadays, a great deal of attention is devoted to the development of best-estimate models able to produce more realistic outcomes. This is also the case for system codes, such as MELCOR, that are being mostly used in a conservative way esp…
View article: Corrigendum: Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part II: application. (2024 J. Phys.: Conf. Ser. 2685 012044)
Corrigendum: Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part II: application. (2024 J. Phys.: Conf. Ser. 2685 012044) Open
Please see Article PDF for corrigendum text.
View article: Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project Open
View article: Current status of MELCOR 2.2 for fusion safety analyses
Current status of MELCOR 2.2 for fusion safety analyses Open
View article: Overview of key thermal–hydraulic phenomena in severe accident unfolding: Current knowledge and further needs
Overview of key thermal–hydraulic phenomena in severe accident unfolding: Current knowledge and further needs Open
Severe Accidents (SA) developments are closely and deeply linked with thermal-hydraulics, that is, fluid flow combined with heat and mass transfer. The present paper synthesizes this relation during an accident unfolding and provides an ov…
View article: Lithium-Lead/water interaction: LIFUS5/Mod3 series E tests analysed by SIMMER-III coupled with RELAP5
Lithium-Lead/water interaction: LIFUS5/Mod3 series E tests analysed by SIMMER-III coupled with RELAP5 Open
The Breeding Blanket is a necessary component to close the nuclear fusion reactor fuel cycle. amongst the most promising conceptual design, there is the Water Cooled Lithium Lead Breeding Blanket, with water as coolant and eutectic Lithium…
View article: PRELIMINARY UNCERTAINTY ASSESSMENT OF THE CONTAINMENT BEHAVIOR
PRELIMINARY UNCERTAINTY ASSESSMENT OF THE CONTAINMENT BEHAVIOR Open
In recent years, an ever-growing attention has been paid to the assessment of the uncertainties linked to simulation results from computer codes employed in the safety analysis of Nuclear Power Plants (NPPs). These codes have been improved…
View article: Uncertainty and Sensitivity Analysis of a Dry Cask for Spent Nuclear Fuel
Uncertainty and Sensitivity Analysis of a Dry Cask for Spent Nuclear Fuel Open
Nuclear safety relies to a good extent on thoroughly validated codes. However, code predictions are affected by uncertainties that need to be quantified for a more accurate evaluation of safety margins. In this regard, the present paper pr…
View article: 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
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 Open
The development and the validation of old and new software in relevant DEMO reactor conditions have been exploited in the latest years within the EUROfusion Consortium. The aim was to use—if possible—the software already validated for fiss…
View article: Post-Test Numerical Analysis of a Helium-Cooled Breeding Blanket First Wall under LOFA Conditions with the MELCOR Fusion Code
Post-Test Numerical Analysis of a Helium-Cooled Breeding Blanket First Wall under LOFA Conditions with the MELCOR Fusion Code Open
The validation of numerical tools employed in the analysis of incidental transients in a fusion reactor is a topic of main concern. KIT is taking part in this task providing both experimental data and by performing numerical analysis in su…
View article: EDUCATION AND TRAINING IN MUSA PROJECT ON MANAGEMENT AND UNCERTAINTIES OF SEVERE ACCIDENTS
EDUCATION AND TRAINING IN MUSA PROJECT ON MANAGEMENT AND UNCERTAINTIES OF SEVERE ACCIDENTS Open
The overall objective of HORIZON 2020 project on “Management and Uncertainties of Severe Accidents (MUSA)” is to quantify the uncertainties of severe accident codes when modelling reactor and spent fuel pools (SFP) accident of Gen II and G…
View article: The EC MUSA Project on Management and Uncertainty of Severe Accidents: Main Pillars and Status
The EC MUSA Project on Management and Uncertainty of Severe Accidents: Main Pillars and Status Open
In the current state of maturity of severe accident codes, the time has come to foster the systematic application of Best Estimate Plus Uncertainties (BEPU) in this domain. The overall objective of the HORIZON-2020 project on “Management a…
View article: Preliminary Analysis of an Aged RPV Subjected to Station Blackout
Preliminary Analysis of an Aged RPV Subjected to Station Blackout Open
Today, 46% of operating Nuclear Power Plants (NPP) have a lifetime between 31 and 40 years, while 19% have been in operation for more than 40 years. Long Term Operation (LTO) is an urgent requirement for all of the nuclear industry. The ai…
View article: Thermal analysis of HI-STORM 100S dry cask with the MELCOR code
Thermal analysis of HI-STORM 100S dry cask with the MELCOR code Open
As spent nuclear fuel (SNF) pools are reaching their capacity, dry storage systems have been introduced worldwide as interim step before permanent deep underground disposal. Thermal behaviour of the SNF, and of the system containing it, ha…
View article: Analysis of Test D1.1 of the LIFUS5/Mod3 facility for In-box LOCA in WCLL-BB
Analysis of Test D1.1 of the LIFUS5/Mod3 facility for In-box LOCA in WCLL-BB Open
View article: RELAP5/SIMMER-III code coupling development for PbLi-water interaction
RELAP5/SIMMER-III code coupling development for PbLi-water interaction Open
View article: Analysis of the Ingress of Coolant Event tests performed in the upgraded ICE facility aimed at the ECART code validation
Analysis of the Ingress of Coolant Event tests performed in the upgraded ICE facility aimed at the ECART code validation Open
View article: ERMSAR 2019 conference of NUGENIA TA2/SARNET on research on severe accidents in nuclear power plants
ERMSAR 2019 conference of NUGENIA TA2/SARNET on research on severe accidents in nuclear power plants Open
View article: Data for: ECART analysis of the STARDUST dust resuspension tests with an obstacle presence
Data for: ECART analysis of the STARDUST dust resuspension tests with an obstacle presence Open
Summary of the experimental resupension data for all the STARDUST tests.
View article: Standalone Containment Analysis of Four Phébus Tests with the ASTEC and the MELCOR Codes
Standalone Containment Analysis of Four Phébus Tests with the ASTEC and the MELCOR Codes Open
After the severe accident (SA) occurred at the Three-Miles Island Nuclear Power Plant (NPP), important efforts on the investigation of the different phenomena during this kind of accidents have been started. Several experimental campaigns …
View article: Presentation of the MUSA Project – Management and Uncertainties of Severe Accidents
Presentation of the MUSA Project – Management and Uncertainties of Severe Accidents Open
View article: ECART analysis of the STARDUST dust resuspension tests with an obstacle presence
ECART analysis of the STARDUST dust resuspension tests with an obstacle presence Open