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Research Article
Mar 7, 2023

Probabilistic Validation: Theoretical Foundation and Methodological Platform

Publication: ASCE-ASME Journal of Risk and Uncertainty in Engineering Systems, Part B: Mechanical Engineering
Volume 9, Issue 2

Abstract

Addressing safety concerns in commercial nuclear power plants (NPPs) often requires the use of advanced modeling and simulation (M&S) in association with the probabilistic risk assessment (PRA). Advanced M&S are also needed to accelerate the analysis, design, licensing, and operationalization of advanced nuclear reactors. However, before a simulation model can be used for PRA, its validity must be adequately established. The objective of this research is to develop a systematic and scientifically justifiable validation methodology, namely, probabilistic validation (PV), to facilitate the validity evaluation (especially when validation data are not sufficiently available) of advanced simulation models that are used for PRA in support of risk-informed decision-making and regulation. This paper is the first in a series of two papers related to PV that provides the theoretical foundation and methodological platform. The second paper applies the PV methodological platform for a case study of fire PRA of NPPs. Although the PV methodology is explained in the context of PRA of the nuclear industry, it is grounded on a cross-disciplinary review of literature and so applicable to validation of simulation models, in general, not necessarily associated with PRA or nuclear applications. This article is available in the ASME Digital Collection at https://doi.org/10.1115/1.4056883.

Information & Authors

Information

Published In

Go to ASCE-ASME Journal of Risk and Uncertainty in Engineering Systems, Part B: Mechanical Engineering
ASCE-ASME Journal of Risk and Uncertainty in Engineering Systems, Part B: Mechanical Engineering
Volume 9Issue 2June 2023

History

Received: Jun 22, 2022
Revision received: Jan 24, 2023
Published online: Mar 7, 2023
Published in print: Jun 1, 2023

Authors

Affiliations

Ha Bui
Socio-Technical Risk Analysis (SoTeRiA) Research Laboratory, Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois Urbana-Champaign (UIUC), Urbana, IL 61801 e-mail: [email protected]
Tatsuya Sakurahara
Socio-Technical Risk Analysis (SoTeRiA) Research Laboratory, Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois Urbana-Champaign (UIUC), Urbana, IL 61801; Illinois Informatics Institute, UIUC, Urbana, IL 61801
Seyed Reihani
Socio-Technical Risk Analysis (SoTeRiA) Research Laboratory, Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois Urbana-Champaign (UIUC), Urbana, IL 61801
Ernie Kee
Socio-Technical Risk Analysis (SoTeRiA) Research Laboratory, Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois Urbana-Champaign (UIUC), Urbana, IL 61801
Zahra Mohaghegh
Socio-Technical Risk Analysis (SoTeRiA) Research Laboratory, Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois Urbana-Champaign (UIUC), Urbana, IL 61801; Illinois Informatics Institute, UIUC, Urbana, IL 61801; Beckman Institute for Advanced Science and Technology, UIUC, Urbana, IL 61801

Funding Information

U.S. Department of Energy10.13039/100000015: DE-NE0008885

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