摘要
结合某CPR1000核电机组设备冷却水系统首批国产化板式换热器在一个燃料循环运行期间的实测数据,评估其换热性能随时间的变化趋势并预测积垢发展规律。利用对数平均温差法计算换热器系数的变化趋势,发现由于工况变化等影响,计算数据无明显变化规律,不利于预判积垢规律,也不利于对比失水事故时的验收标准。根据换热器运行期间流量变化范围和制造厂提供的仿真数据,逆向拟合得到新的换热器系数计算公式,并以此换算得到对应失水事故时的换热数据。研究表明,该型换热器实际换热性能较设计值的裕量大,换热性能随运行时间呈现明显的结垢规律,但污垢沉积较慢,完全满足核电机组失水事故时的换热能力需求。
Based on the measured data during one fuel operation cycle of the first batch of domestic plate heat exchanger in the cooling water system of a CPR1000 nuclear power unit, the trend of heat transfer performance is evaluated and the development rule of crud is predicted. It is found that there is no obvious rule in the calculation data due to the influence of varying working condition, which is not conducive to the prediction of crud rule and the comparison of acceptance standards in case of water loss accident. According to the varying range of fluid during the operation of heat exchanger and the simulation data provided by the manufacturer, a new calculation formula of heat exchanger factor is obtained by inverse fitting, and the corresponding heat exchange data in case of water loss accident is obtained by conversion. The results show that the actual heat exchange performance of this type of heat exchanger is better than the design value, and the heat exchange performance presents obvious scaling law with the operation time, but the fouling deposition is slow,which fully meets the heat exchange capacity demand of the nuclear power unit in the event of water loss accident.
作者
杨璋
舒相挺
徐逸哲
蒋彦龙
YANG Zhang;SHU Xiang-tinG;XU Yi-zhe(Key Laboratory of Aircraft Environment Control and Life Support,MIIT,Nanjing University of Aeronautics&Astronautics;Ningde Nuclear Power Company)
出处
《电站系统工程》
2020年第6期67-70,共4页
Power System Engineering
关键词
核电厂
板式换热器
安全准则
污垢
换热性能
nuclear power plant
plate heat exchanger
safety criteria
fouling
heat transfer capacity
作者简介
杨璋(1981-),研究员级高级工程师。江苏南京,210016。
