Calculation and Test of Core Flow Rate Distribution of China Experimental Fast Reactor

Based on the core and primary circuit design of China Experimental Fast Reactor（CEFR）,a multiple-channel thermal-hydraulic analysis code DAEMON was developed to calculate the core flow rate distribution and unsymmetric coefficient in different conditions.In the commissioning stage,a series of full-scale tests for reactor core were performed in CEFR with a permanent-magnet sodium flow meter.The numerical results of code DAEMON showed a good agreement with test data.The core hydraulic design was also validated with a view to the requirements of design criteria,commissioning and operation specifications.