Uncertainty quantification application on the Phebus FPT1 using the coupling of MELCOR and DAKOTA in a Python environment/architecture

• MUSA project provided a harmonized approach for uncertainty analysis of Severe Accidents. • Phebus FPT1 has been used to test uncertainty methodology. • MELCOR-DAKOTA coupling in a Python environment/architecture is presented. 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.

Authors

Institutions

Publication Details

Journal
Nuclear Engineering and Design
Published
2025-05-22
DOI
https://doi.org/10.1016/j.nucengdes.2025.114135
Citations
1
Primary Topic
Nuclear Engineering Thermal-Hydraulics
Type
article
Field-Weighted Citation Impact
4.99

Funders

Controls
|||
ALL TIME
JAN
FEB
MAR
APR
MAY
JUN
JUL
AUG
SEP
OCT
article

Uncertainty quantification application on the Phebus FPT1 using the coupling of MELCOR and DAKOTA in a Python environment/architecture

G. Agnello, Mattia Massone, F. Mascari
1 citations
Nuclear Engineering and Design
Nuclear Engineering Thermal-Hydraulics
4.99
article

Uncertainty quantification application on the Phebus FPT1 using the coupling of MELCOR and DAKOTA in a Python environment/architecture

G. Agnello, Mattia Massone, F. Mascari
article en
1 citations

Abstract

• MUSA project provided a harmonized approach for uncertainty analysis of Severe Accidents. • Phebus FPT1 has been used to test uncertainty methodology. • MELCOR-DAKOTA coupling in a Python environment/architecture is presented. 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.

Nuclear Engineering and DesignVol. 441
National Agency for New Technologies, Energy and Sustainable Economic Development (IT), University of Palermo (IT), University of Bologna (IT)
H2020 Euratom
Life in Land
Openalex Percentile: Top 6%
Nuclear Engineering Thermal-Hydraulics
4.99
AI Navigator

Ask Laika to Summarize, Analyze, and Connect papers live on the map.

Summarize Papers & Methodologies

Extract key findings, datasets, and comparative methods across publications.

Benchmark Rankings & Visual Analytics

Rank top research institutions, authors, funders, topics, and journals by Field-Weighted Citation Impact (FWCI) and paper volume with instant charts.

Connect Distant Disciplines

Bridge topological clusters on the map to find hidden collaborative intersections.