某核电机组凝结水溶解氧超标问题分析及试验研究

发布时间：2018-10-07 21:23

【摘要】：结合核电机组的运行特点与溶解氧存在机理,对某核电机组凝结水溶解氧超标问题进行系统性分析和试验研究。着手从漏气量检查、凝汽器性能确认、真空泵抽气能力等3方面进行了分析,研究发现漏气量应参照ASME PTC12.2的规定控制,核电机组凝汽器过冷度对凝结水溶解氧的影响约为理论计算值的1/5-1/3,通过提升真空泵抽气能力提高凝汽器真空度约4 k Pa时能同比降低溶解氧量约5×10~(-9)。通过减小漏气量、提升真空泵抽气能力最终将溶解氧控制在3×10~(-9)的期望值内,有效处理核电机组凝结水溶解氧超标问题。避免了因凝结水溶氧超标带来的压水堆核电机组产生水腐蚀产物的严重后果。为后续类似问题的处理以及在行业内制定严格的凝结水溶氧控制标准提供了借鉴。
[Abstract]:Combined with the operation characteristics of nuclear power unit and the existence mechanism of dissolved oxygen, the problem of excess of dissolved oxygen in condensate of a nuclear power unit is systematically analyzed and tested. Starting from three aspects of air leakage inspection, condenser performance confirmation, vacuum pump air extraction capacity, etc., it is found that the air leakage should be controlled by referring to the regulation of ASME PTC12.2. The effect of supercooling of condenser on dissolved oxygen in condensate of nuclear power unit is about 1 / 5 / 1 / 3 of the theoretical calculated value. When the vacuum degree of condenser is increased about 4 k Pa, the dissolved oxygen content can be reduced by 5 脳 10 ~ (-9). By reducing the amount of gas leakage and increasing the pumping capacity of vacuum pump, the dissolved oxygen is controlled within the expected value of 3 脳 10 ~ (-9), and the problem of excess of dissolved oxygen in condensate of nuclear power unit is effectively dealt with. The water corrosion product of PWR nuclear power unit caused by the excess of dissolved oxygen in condensate water is avoided. It provides a reference for the treatment of similar problems and the establishment of strict control standards for dissolved oxygen in condensate water in the industry.
【作者单位】：南京航空航天大学宇航学院;中广核工程设计有限公司;
【分类号】：TM623.91

【共引文献】