【作者】 姜峰；

【导师】 常发亮； 孟强；

【作者基本信息】 山东大学 ， 控制工程（专业学位）， 2019， 硕士

【摘要】 高温气冷堆核电站示范工程是我国首个自主研发的具有第四代核电特性的核电站,它采用两个核蒸汽供应系统模块驱动一台汽轮发电机运行发电的结构形式。由DCS实现的全厂功率控制系统是全厂协调控制的核心。蒸汽发生器出口温度控制系统是全厂功率控制系统的典型子系统之一,其涉及的蒸汽发生器、主氦风机均为首次制造,各特性曲线及控制系统的整定值均未给出,当前设计方寄希望于由调试人员现场试验直接获得。调试人员在对现场设备掌握不透彻的情况下盲目试验,存在一定的设备损坏及人身伤害风险。为探索系统的特性曲线及控制参数,本文选择从蒸汽发生器出口温度控制系统作为突破点进行分析优化。本文通过分析高温气冷堆核电站示范工程一回路主设备——主氦风机的参数,利用能量守恒公式推导计算建立了高温气冷堆一回路氦气质量流量——转速模型,得出理论流量——转速特性曲线,并通过分析压力、温度对质量流量的影响得出质量流量补偿公式。通过分析高温气冷堆蒸汽发生器的特殊结构,利用传热公式建立蒸汽发生器的传热模型,得到蒸汽发生器出口蒸汽温度与一回路氦气流量之间的关系。应用MATLAB仿真工具构建蒸汽发生器出口蒸汽温度控制与氦气流量控制系统串级控制模型,通过比对系统的阶跃响应曲线,对串级控制的副回路、主回路进行理论参数整定。经过反复试验,最终得出理论整定值,从理论上实现了稳态偏差小于±2℃,动态偏差小于5℃/-10℃的调节目标。通过修改模型参数分析系统的阶跃响应,得出理论整定值的适用范围。本文还分析提出了系统硬件的优化、逻辑组态的优化,保证了现场控制系统的安全稳定运行。通过理论分析及计算得出的控制模型及整定参数,为今后开展现场调试工作积累了丰富的经验。更多还原

【Abstract】 High Temperature Reactor-Pebblebed Modules(HTR-PM)is the first independently developed nuclear power plant with the fourth generation nuclear power characteristics in China.It uses two nuclear steam supply system modules to drive a turbogenerator to run and generate electricity.The power control system of the whole plant realized by DCS is the core of the whole plant power control system.The temperature control system of the steam generator outlet is one of the typical subsystems of the whole plant power control system.The steam generator and the main helium blower involved in the system are manufactured for the first time.The characteristic curves and setting values are not given.At present,the designer hopes that they can be obtained directly by the field test of the debugger.There are some risks of equipment damage and personal injury when the debugger blindly tests the field equipment without thorough knowledge of it.In order to explore the characteristic curve and control parameters of the system,this paper chooses the outlet temperature control system of steam generator as a breakthrough point to analyze and optimize.By analyzing the parameters of the main helium blower in the primary loop of HTR-PM,this paper calculates and establishes the helium mass flow and speed model in the primary loop of high temperature gas-cooled reactor,obtains the characteristic table of theoretical flow and speed,and obtains the mass flow compensation formula by analyzing the influence of pressure and temperature on mass flow rate.By analyzing the special structure of the steam generator of high temperature gas cooled reactor,the heat transfer model of the steam generator is established by using the heat transfer formula,and the relationship between the steam temperature at the outlet of the steam generator and the helium flow rate in the first loop is obtained.The cascade control model of steam generator outlet steam temperature control and helium flow control system is built by using MATLAB simulation tool.By comparing the step response curve of the system,the theoretical parameters of the secondary and main circuits of the cascade control are tuned.After repeated tests,the theoretical setting value is finally obtained,and the program adjustment standard with steady-state deviation less than ±2°C and dynamic deviation less than 5 C/-10℃ is theoretically realized.By modifying the parameters of the model to analyze the step response of the system,the applicable range of the theoretical setting value is obtained.The optimization of hardware and logic configuration of the system is also analyzed and put forward to ensure the safe and stable operation of the field control system.According to the results of theoretical analysis and calculation,we can accumulates many debugging experience which means a lot for future work.更多还原