Development of a systematic approach for quantification of thermal hydraulic code model input uncertainty - IRSN - Institut de radioprotection et de sûreté nucléaire
Communication Dans Un Congrès Année : 2019

Development of a systematic approach for quantification of thermal hydraulic code model input uncertainty

Résumé

Uncertainty analysis (UA) is a key element in nuclear power plant (NPP) deterministic safety analysis using best-estimate thermal hydraulic codes and best estimate plus uncertainty (BEPU) methodologies. If forward uncertainty propagation methods have now become mature for industrial applications, the input uncertainties quantification (IUQ) on the physical models still requires further investigations. The OECD/NEA PREMIUM project attempted to benchmark the available IUQ methods, but observed a strong user-effect due to lack of best practices guidance. The SAPIUM project has been proposed towards the construction of a clear and shared systematic approach for input uncertainty quantification as it is already addressed in industries and R&D for related topics. The main outcome of the project is a first “good practices” document that can be exploited for safety study in order to reach consensus among experts on recommended practices as well as to identify remaining open issues for further developments. This paper presents the systematic approach that consists in five elements in a step by step approach to perform a meaningful model input uncertainty quantification & validation, the key issues to be addressed for each step as well as some “good practice guidelines” recommendations and open issues on the tools and methods to be used for each step.
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Dates et versions

cea-04378696 , version 1 (08-01-2024)

Identifiants

  • HAL Id : cea-04378696 , version 1

Citer

Jean Baccou, Jinzhao Zhang, Philippe Fillion, Guillaume Damblin, Alessandro Petruzzi, et al.. Development of a systematic approach for quantification of thermal hydraulic code model input uncertainty. NURETH2019 - 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2019, Portland (OR), United States. pp.3054-3067. ⟨cea-04378696⟩
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