Giuseppe Agnello , Mattia Massone , Fulvio Mascari
{"title":"Uncertainty quantification application on the Phebus FPT1 using the coupling of MELCOR and DAKOTA in a Python environment/architecture","authors":"Giuseppe Agnello , Mattia Massone , Fulvio Mascari","doi":"10.1016/j.nucengdes.2025.114135","DOIUrl":null,"url":null,"abstract":"<div><div>During the last few years, the international nuclear scientific community involved in the development of deterministic safety analyses in the Severe Accident (SA) domain has focused its interest on the analysis of methodologies for the uncertainty quantification using the state-of-art integral SA codes (e.g. ASTEC, MAAP, MELCOR, etc.). Within this framework, the H2020 “Management and Uncertainty of Severe Accidents” (MUSA) project, coordinated by CIEMAT (Spain), aimed to establish a harmonized approach for the application of uncertainty quantification methodologies to SAs. Along with the MUSA Working Package named “Application of UQ Methods against Integral Experiments”, coordinated by ENEA (Italy), the uncertainty analysis methodology has been applied to the Phebus FPT1 experiment. To develop the reference base case, the integral code MELCOR 2.2 has been selected, and it has been coupled with the uncertainty tool DAKOTA to develop the uncertainty analysis. The study has been focused on the degradation and beginning of the aerosol phase of the test, considering the MELCOR aerosol miscellaneous constants as uncertain input parameters and the maximum value of the total mass of aerosol in suspension in the containment atmosphere as Figure of Merit (FOM). The uncertainty analysis permitted a first estimation of the uncertainty bandwidth of the FOM, comparing it with the experimental and reference case values. Among the uncertain input parameters, the dynamic shape factor and the agglomeration shape factor present, respectively, a moderate and significant statistical correlation with the FOM.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"441 ","pages":"Article 114135"},"PeriodicalIF":2.1000,"publicationDate":"2025-05-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325003127","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
During the last few years, the international nuclear scientific community involved in the development of deterministic safety analyses in the Severe Accident (SA) domain has focused its interest on the analysis of methodologies for the uncertainty quantification using the state-of-art integral SA codes (e.g. ASTEC, MAAP, MELCOR, etc.). Within this framework, the H2020 “Management and Uncertainty of Severe Accidents” (MUSA) project, coordinated by CIEMAT (Spain), aimed to establish a harmonized approach for the application of uncertainty quantification methodologies to SAs. Along with the MUSA Working Package named “Application of UQ Methods against Integral Experiments”, coordinated by ENEA (Italy), the uncertainty analysis methodology has been applied to the Phebus FPT1 experiment. To develop the reference base case, the integral code MELCOR 2.2 has been selected, and it has been coupled with the uncertainty tool DAKOTA to develop the uncertainty analysis. The study has been focused on the degradation and beginning of the aerosol phase of the test, considering the MELCOR aerosol miscellaneous constants as uncertain input parameters and the maximum value of the total mass of aerosol in suspension in the containment atmosphere as Figure of Merit (FOM). The uncertainty analysis permitted a first estimation of the uncertainty bandwidth of the FOM, comparing it with the experimental and reference case values. Among the uncertain input parameters, the dynamic shape factor and the agglomeration shape factor present, respectively, a moderate and significant statistical correlation with the FOM.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.