Thermal-fluid validation tests of prototype Gen-IV SFR

The current study is to generate test DBs of IHX flow characteristics and reactor flow distribution and to develop basic design of core receptacle and IHX inlet gas entrainment performance test facilities for SFR thermal fluidic design validation. IHX facilities were constructed based on same hydraulic diameter, Re number and flow area ratio as prototype. The ensemble averaged test data at optimized points were generated including intensive uncertainty analysis. To additionally quantify the scale distortion at exit due to slab geometry of test section, a supplementary experiment was also performed. The test DB will be utilized for validation of design code, SHXSA. Reactor flow distribution test facilities were designed based on the 1/5 linear scale, shape and EU number preservation. The design of core/IHX simulator were uniquely developed, which is proved by patent. All the simulators were calibrated precisely at specially provided loop and the 336 pressure impulse lines were successfully drawn out from reactor vessel without perturbation of major flow. A preliminary CFD analysis shows the rationality of test facilities design and supplies requirement of instrumentations. During the process, the prototype PHTS pump Y-junction piping shape was improved. Test DB was generated based on a proper test procedure and satisfied the test requirement, which will be included in the safety analysis report of PGSFR. The receptacle test facilities were designed based on the same scale, shape, water as working fluid and same Re number as prototype. A rotational orifice concept is uniquely adopted for the design, which was validated using CFD. For the IHX inlet gas entrainment, a basic design were performed. A transparent acrylic material was selected for the visualization of multi-dimensional flow behaviour. The test DB will contribute to confirmation of the PGSFR safety and operational margin