核反应堆压力容器小破口事故中坍塌液位的测量  

Liquid collapse level monitoring for nuclear reactors during loss of coolant accident

作　　者：李胜强[1] 薄涵亮[1] 王文然[1] 姜胜耀[1] 

机构地区：[1]清华大学核能与新能源技术研究院,先进反应堆工程与安全教育部重点实验室,北京100084

出　　处：《清华大学学报（自然科学版）》2009年第6期872-875,共4页Journal of Tsinghua University(Science and Technology)

摘　　要：核反应堆冷却剂液位是重要的安全参数,而压力容器破口事故(LOCA)下更加需要测量坍塌液位来反映堆芯冷却状态。该文针对差压式液位测量方法在破口事故下的特性进行了理论分析和试验研究。分析表明:喷放附加压降和喷放引起的压力波振荡都可能造成对于差压式测量方法产生附加的扰动;其中以压力波影响为主。实验结果说明:压力波振荡等影响造成差压液位测量结果产生峰值不大于2.5%的附加误差,这在破口事故下属于测量精度允许范围。因此,差压方法在压力容器小破口事故下仍能正确反映容器内坍塌液位,即容器的液体装量。The coolant level is an important parameter for nuclear reactor cooling systems, especially in loss of coolant accidents （LOCA）. The differential pressure characteristics of level meter during such accidents were studied theoriticlly and exeperimentally. The pressure waves and addition pressure drops are found to affect the measurements. The error caused by pressure waves is larger, but the experiments show that the total error will he less than 2.5 %, which is acceptable for the loss of coolant accidents. Thus, the differential pressure gauges can provide accurate collapse level data, even during the accidents.

关 键 词：核反应堆 液位测量 破口事故 

分 类 号：TL364[核科学技术—核技术及应用] TK313[动力工程及工程热物理—热能工程]