Development of good practice guidance for quantification of thermal-hydraulic code model input uncertainty

Autor: Takeshi Takeda, Jinzhao Zhang, Francesc Reventos, Alessandro Petruzzi, Deog-Yeon Oh, Rafael Mendizábal, T. Skorek, Jean Baccou, Guillaume Damblin, Mathieu Couplet, Philippe Fillion, Bertrand Iooss
Přispěvatelé: PSN-RES/SEMIA, Institut de Radioprotection et de Sûreté Nucléaire (IRSN), CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Universitat Politècnica de Catalunya [Barcelona] (UPC), Service de Maîtrise des Incidents et Accidents (IRSN/PSN-RES/SEMIA)
Jazyk: angličtina
Rok vydání: 2019
Předmět:
Zdroj: Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2019, 354, ⟨10.1016/j.nucengdes.2019.110173⟩
Nuclear Engineering and Design, 2019, 354, ⟨10.1016/j.nucengdes.2019.110173⟩
ISSN: 0029-5493
1872-759X
Popis: International audience; Taking into account uncertainties is a key issue in nuclear power plant safety analysis using best estimate plus uncertainty methodologies. It involves two main types of treatment depending on the variables of interest: input parameters or system response quantity. The OECD/NEA PREMIUM project devoted to the first type of variables has shown that inverse methods for input uncertainty quantification can exhibit strong user-effect. One of the main reasons was the lack of a clear guidance to perform a reliable analysis. This work is precisely devoted to the development of a first good practice guidance document for quantification of thermal-hydraulic code model input uncertainty. The developments have been done in the framework of the OECD/NEA SAPIUM project (January 2017-September 2019). This paper provides a summary of the main project outcome. Recommendations and open issues for future developments are also given.
Databáze: OpenAIRE