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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。
Combining with the operation characteristics of nuclear power unit and the existence mechanism of dissolved oxygen, the systematic analysis and experimental research on the problem of excessive dissolved oxygen in condensate water of a nuclear power unit are carried out. Starting from the leakage check, condenser performance confirmation, vacuum pump suction capacity and other aspects were analyzed, the study found that the amount of leakage should be controlled according to the provisions of ASME PTC12.2, the supercooling of condenser condensate The effect of dissolved oxygen is about 1 / 5-1 / 3 of the theoretical value, which can reduce the dissolved oxygen content by about 5 × 10 -9 by increasing the pumping capacity of the vacuum pump and increasing the condenser vacuum by 4 kPa. . By reducing the amount of blow-by gas and increasing the pumping capacity of the vacuum pump, the dissolved oxygen is finally controlled within the expected value of 3 × 10 -9 so as to effectively deal with the excessive dissolved oxygen in the condensate of nuclear power plants. Avoiding the serious consequences of water corrosion products from pressurized water reactor nuclear power plants due to excessive dissolved oxygen in condensate water. It provides reference for the follow-up of similar problems and the formulation of strict control standards of dissolved oxygen in the industry.