摘要
核电站反应堆功率控制系统是核电站的关键控制系统之一,在开环测试的环境下,控制系统无正确、有效的对象特性反馈,无法验证功率控制系统的设计和功能实现是否正确。基于REMARK堆芯物理程序,建立了某压水堆核电站堆芯物理模型程序,为反应堆功率控制系统的设计和验证提供控制对象。堆芯模型采用三维有限差分网格进行求解计算,两群时间相关的三维扩散方程能够对快中子和热中子注量率行为进行准确模拟。将堆芯物理模型计算的反应性系数,包括硼微分价值参数、慢化剂温度系数、等温温度系数、多普勒功率系数以及功率调节棒组和停堆棒组的反应性价值,与核电厂的堆芯设计参考数据进行对比。通过对比分析发现,模型的计算结果与电厂堆芯的设计参考数据吻合,说明所建立的堆芯模型能够有效反映电厂反应堆的堆芯物理特性。该堆芯模型可与反应堆功率控制系统构成有效的闭环测试环境,为反应堆功率控制系统的设计和验证提供有效手段。
The power control system of reactor core is one of the critical control systems in nuclear power plant, under the environment of open loop test, the control system does not have correct and effective object characteristics feedback, so it is impossible to verify whether the design and functional implementation of the power control system are correct or not. Based on REMARK reactor core physical program,the physical model program of the reactor core of certain PWR nuclear power plant is established, to provide control object for design and verification of the reactor power control system. The three - dimensional finite difference grid is used to solve the calculation, and the two - group of time dependent three - dimensional diffusion equation can accurately simulate the behavior of fast neutron and thermal neutron flux rate. The reactivity coefficients calculated by the model, including the moderator temperature coefficient isothermal temperature coefficient, Doppler power coefficient and Boron differential value, and all reactivity values of power control rod group and shutdown rod group are compared with the reference data in design of reactor core. Through the comparative analysis, it is found that the simulation results are identical with the design reference data,which shows that the model is correct and effective,and can reflect the physical characteristics of the reactor core. Effective closed loop test environment can be composed of this model and the power control system of the reactor core ; the model provides effective means for designing and verifying the power control system of the reactor.
出处
《自动化仪表》
CAS
2017年第5期7-10,14,共5页
Process Automation Instrumentation
基金
国家重大科技专项基金资助项目(2013ZX06005001)
关键词
能源
核电站
压水堆
反应堆堆芯
功率控制
闭环
Energy
Nuclear power plant
Pressurized water reactor
Reactor core
Power control
Closed loop
