A global sensitivity analysis framework for guiding the design improvement of new concepts of small modular reactors

• A GSA framework is proposed to guide the design improvement of SMRs. • The OT-based GSA indices are used to identify the most important inputs. • CUSUNORO is used to identify the safety critical ranges of the inputs. • A NPP with four SMDFR, a new concept of SMR, is considered as case study. • The identified design improvements ensure the safe operation of the NPP. Small Modular Reactors (SMRs) are new concepts of Nuclear Power Plants (NPPs) whose safety assessment typically cannot rely on design-specific operational experience and field data. Assessing their safety requires a careful combination of engineering expertise, and of physical (laboratory) and virtual (simulation) experiments. Modeling the system response accurately, in consideration of the engineering design and physical aspects of SMRs requires computationally burdensome computer models. Although interpretable, it is difficult to consistently identify the most important inputs and provide safety margins, especially for high-dimensional correlated inputs and outputs. To address these issues, we propose a Global Sensitivity Analysis (GSA) framework that combines recently introduced global sensitivity indices based on Optimal Transport (OT) with a graphical visualization tool based on CUmulative SUm of NOrmalized Reordered Output (CUSUNORO). The OT-based indices allow us to identify the most important inputs, whereas the graphical representation of the latter enables us to identify the safety critical ranges of these inputs. The proposed framework is applied to a demonstrative case study concerning Small Modular Dual Fluid Reactors (SMDFRs), a new SMR concept. The numerical experiments show how the approach can help interpreting the simulation results and suggesting design improvements to keep operational settings away from the Critical failure Region (CR).

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Publication Details

Journal
Nuclear Engineering and Design
Published
2025-08-26
DOI
https://doi.org/10.1016/j.nucengdes.2025.114398
Citations
1
Primary Topic
Probabilistic and Robust Engineering Design
Type
article
Field-Weighted Citation Impact
1.40
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article

A global sensitivity analysis framework for guiding the design improvement of new concepts of small modular reactors

Enrico Zio, Elmar Plischke, Stefano Marchetti, Francesco Di Maio et al.
1 citations
Nuclear Engineering and Design
Probabilistic and Robust Engineering Design
1.40
article

A global sensitivity analysis framework for guiding the design improvement of new concepts of small modular reactors

Enrico Zio, Elmar Plischke, Stefano Marchetti, Francesco Di Maio, Emanuele Borgonovo
article en
1 citations

Abstract

• A GSA framework is proposed to guide the design improvement of SMRs. • The OT-based GSA indices are used to identify the most important inputs. • CUSUNORO is used to identify the safety critical ranges of the inputs. • A NPP with four SMDFR, a new concept of SMR, is considered as case study. • The identified design improvements ensure the safe operation of the NPP. Small Modular Reactors (SMRs) are new concepts of Nuclear Power Plants (NPPs) whose safety assessment typically cannot rely on design-specific operational experience and field data. Assessing their safety requires a careful combination of engineering expertise, and of physical (laboratory) and virtual (simulation) experiments. Modeling the system response accurately, in consideration of the engineering design and physical aspects of SMRs requires computationally burdensome computer models. Although interpretable, it is difficult to consistently identify the most important inputs and provide safety margins, especially for high-dimensional correlated inputs and outputs. To address these issues, we propose a Global Sensitivity Analysis (GSA) framework that combines recently introduced global sensitivity indices based on Optimal Transport (OT) with a graphical visualization tool based on CUmulative SUm of NOrmalized Reordered Output (CUSUNORO). The OT-based indices allow us to identify the most important inputs, whereas the graphical representation of the latter enables us to identify the safety critical ranges of these inputs. The proposed framework is applied to a demonstrative case study concerning Small Modular Dual Fluid Reactors (SMDFRs), a new SMR concept. The numerical experiments show how the approach can help interpreting the simulation results and suggesting design improvements to keep operational settings away from the Critical failure Region (CR).

Nuclear Engineering and DesignVol. 444
Clausthal University of Technology (DE), Centre de Recherche sur les Risques et les Crises (FR), Bocconi University (IT), Politecnico di Milano (IT)
Openalex Percentile: Top 14%
Probabilistic and Robust Engineering Design
1.40
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