Development of three-dimensional hot pool model in a system analysis code for pool-type FBR

A three-dimensional hot pool analysis code with SIMPLE algorithm was developed based on staggered grid, which can predict thermal-hydraulic characteristic in hot pool of pool-type liquid metal fast breeder reactor (LMFBR) under Cartesian and cylindrical coordinate systems. After being incorporated into system analysis code for pool-type fast reactor in China (SAC-CFR), the coupled code was used to analyze the thermal-hydraulic behavior in the upper plenum of fast breeder reactor “MONJU” during reactor scram transient. A basic agreement was obtained, which means the present model is effective. And then the coupled code with newly developed porous medium model was used to analyze the flow field in China Experimental Fast Reactor hot pool under steady-state operation condition. The distribution characteristic of flow field in hot pool showed the effectiveness of porous medium model, which formed preparations for further development of passive residual heat removal system in-vessel.

► A 3-D hot pool analysis code with porous medium model was developed.
► The coupling between 3-D model and system analysis code was finished.
► The coupled code was used to analyze T-H behavior in upper plenum of MONJU.
► Complex flow field in CEFR hot pool was analyzed with the coupled code.