ACP100S浮动核电站核蒸汽供应系统控制系统分析与仿真研究
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摘要
作为核能在海上应用的新的方式,浮动核电站为在不同区域灵活部署和利用核能创造了条件.该研究从ACP100S浮动核电站使用要求、主要系统设备运行要求、机组配置要求及海洋环境要求等多方面开展了ACP100S核蒸汽供应系统的控制系统要求分析,给出了控制系统方案.以此为基础,利用RELAP系统分析程序和控制系统仿真程序MATLAB/SIMULINK,开展了控制系统数值仿真分析工作.仿真结果满足控制系统验收准则要求,验证了控制系统设计的有效性.
As a new way to apply nuclear energy in the sea,floating nuclear power plant( FNPP) creates conditions for flexible deployment and use of nuclear energy in different regions.In this paper,the requirement analysis and plan analysis of control systems for nuclear steam supply system of ACP100 S are carried out in several aspects,including the characteristics of the use of the nuclear power plant,the operation of main systems and equipments,the configuration of the unit,and the characteristics of the marine environment,etc.The scheme of the above control systems are put forward.On the basis of this,the numerical simulation analysis of the control system is carried out by using the system analysis program RELAP and the control system simulation program MATLAB/SIMULINK.The simulation results meet the requirements of the acceptance criteria of the control system and verify the effectiveness of the control system.
As a new way to apply nuclear energy in the sea,floating nuclear power plant( FNPP) creates conditions for flexible deployment and use of nuclear energy in different regions.In this paper,the requirement analysis and plan analysis of control systems for nuclear steam supply system of ACP100 S are carried out in several aspects,including the characteristics of the use of the nuclear power plant,the operation of main systems and equipments,the configuration of the unit,and the characteristics of the marine environment,etc.The scheme of the above control systems are put forward.On the basis of this,the numerical simulation analysis of the control system is carried out by using the system analysis program RELAP and the control system simulation program MATLAB/SIMULINK.The simulation results meet the requirements of the acceptance criteria of the control system and verify the effectiveness of the control system.
引文
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[7]YIN S S,TIAN Y J,QIU S Z,et al.Accident process and core thermal response during a station blackout initiated study for small modular reactor[J]. Frontiers in energy research,2018,6(43):1-5.
[8]曾未,宋丹戎,陈智,等.ACP100+失水事故应对策略研究[J].核动力工程,2017,38(6):72-75.
[9]汪量子,巨海涛,秦冬,等.模块式小型压水堆ACP100堆芯燃料管理策略研究[J].核动力工程,2018,39(1):157-160.
[2]王玮,刘聪,陈智,等,浮动式核电站载体初步技术方案研究[J].科技视界,2015(36):37-38.
[3]张延昌,景宝金,童波,等.浮动核电站载体平台安全性设计初探[J].船舶,2017(3):1-9.
[4]YE X L,SUN H J,GAO S,et al.Turbine oil in service from deterioration from offshore floating nuclear power plant[J]. Nuclear science and technology,2017,5(4):204-210.
[5]高颖贤,申亚欧,曾未.安注箱堆小型模块化压水堆LOCA的影响研究[J].核动力工程,2015,36(6):45-49.
[6]邱志方,邓坚,陈红霞,等.模块式小堆超压风险及设计优化研究[J].原子能科学技术,2016,50(1):113-117.
[7]YIN S S,TIAN Y J,QIU S Z,et al.Accident process and core thermal response during a station blackout initiated study for small modular reactor[J]. Frontiers in energy research,2018,6(43):1-5.
[8]曾未,宋丹戎,陈智,等.ACP100+失水事故应对策略研究[J].核动力工程,2017,38(6):72-75.
[9]汪量子,巨海涛,秦冬,等.模块式小型压水堆ACP100堆芯燃料管理策略研究[J].核动力工程,2018,39(1):157-160.