Validation of APROS code against experimental data from a Lead-Bismuth Eutectic thermal-hydraulic loop

APROS is a multifunctional simulator, suitable for various tasks throughout the complete power plant life cycle from design to operator training. The code combines the System-Thermal Hydraulics (STH) capabilities with 1D/3D reactor core neutronics and full automation system modelling. APROS is widely used for dynamic studies in light water nuclear reactor technology. Currently the simulation capabilities of the code are being developed for evaluation of Generation IV nuclear reactor designs that use liquid metals (e.g. Lead-Bismuth Eutectic (LBE) alloy) as cooling media. However, validation of APROS code has been limited to light water cooled systems (test facilities and reactors). Therefore validation is required for the LBE thermal-hydraulic models. In this work, we use data from the Thermal-hydraulic Accelerator-Driven System (ADS) Lead bismuth Loop (TALL) facility constructed at KTH. In total, 10 transient data sets from TALL experiments were used for APROS LBE fluid model integral validation. TALL facility model consisting of the primary LBE loop, the secondary oil loop and the ultimate water heat sink was developed using APROS Graphical User Interface (GUI). Five System Response Quantities (SRQs) were considered in the validation process: LBE temperatures at four locations of the facility and the LBE mass flow. Uncertainty analysis was employed in the validation process. Results of quantitative code validation are presented in the paper. Suggestions for improvements of the validation methodology, experimental conditions and approaches to reduction of experimental uncertainty are discussed in detail.