ACME试验台架典型小破口工况试验及数值分析

摘要

对我国首个大型非能动堆芯冷却系统整体试验台架(ACME)中的典型小破口事故进行了试验及数值分析.分析结果表明:在ACME上开展的典型小破口试验,其事故序列及试验现象符合预期;RELAP5数值分析的主要结果能较好地反映试验现象,与试验结果吻合良好;堆芯棒束区相间摩擦模型的选用对堆芯坍塌液位的计算有较大影响,在不同阶段选用不同的模型可使计算结果更好地与试验值相匹配.%To study the typical small break loss of coolant accidents(SBLOCAs)on the Advanced Core-cooling Mechanism Experiment(ACME),which was the first integral test facility on passive core cooling system of nuclear power plant in domestic,the experimental and numerical analyses were carried out.The analysis results show that the accident chronology and major thermal-hydraulic phenomena of typical SBLOCAs on ACME are as to be expected,and the numerical results of RELAP5 model and experimental results are highly consistent.The interfacial drag model in rod bundle geometry has a great effect on reactor core collapsed level calculation,and different models adopted during different accident processes will guarantee better match between calculation values and experimental values.