Calculation and Test of Core Flow Rate Distribution of China Experimental Fast Reactor
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摘要: 针对中国实验快堆(CEFR)堆芯和一回路的设计特点,开发水力特性计算程序DAEMON,完成不同工况下的全堆芯流量分配计算,给出流量分配不均匀性等参数。在反应堆调试阶段,进行全堆芯流量分配试验。结果表明,程序计算值与试验值符合较好。在此基础上,验证了CEFR堆芯的流体力学设计,并为反应堆调试和运行提供了基础数据。Abstract: 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.
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