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

J. Baccou (1) , J. Zhang , P. Fillion (2) , G. Damblin (2) , A. Petruzzi , R. Mendizábal , F. Reventós (3) , T. Skorek , M. Couplet , B. Iooss , D.-Y. Oh , T. Takeda

1 IRSN/PSN-RES/SEMIA - Service de Maîtrise des Incidents et Accidents
2 CEA-DES (ex-DEN) - CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire)
3 UPC - Universitat Politècnica de Catalunya = Université polytechnique de Catalogne [Barcelona]

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.

Domaines: Sciences de l'ingénieur [physics]

J. Baccou, J. Zhang, P. Fillion, G. Damblin, A. Petruzzi, et al.. Development of good practice guidance for quantification of thermal-hydraulic code model input uncertainty. Nuclear Engineering and Design, 2019, 354, ⟨10.1016/j.nucengdes.2019.110173⟩. ⟨hal-02530001⟩