小型压水堆功率控制系统堆芯换热系数不确定性量化研究  

The Quantitative Study on the Uncertainty of the Core Heat Transfer Coefficient for the Power Control System of Small Pressurized Water Reactor

作　　者：曾文杰 厉晓玉[2] 谢金森 赵守智[1] ZENG Wenjie;LI Xiaoyu;XIE Jinsen;ZHAO Shouzhi(Department of Reactor Engineering,China Institute of Atomic Energy,Beijing 102413,China;School of Nuclear Science and Technology,University of South China,Hengyang of Hunan Prov.,421001,China)

机构地区：[1]中国原子能科学研究院反应堆工程研究设计所,北京102413 [2]南华大学核科学技术学院,湖南衡阳421001

出　　处：《核科学与工程》2024年第4期756-764,共9页Nuclear Science and Engineering

基　　金：国家自然科学基金青年项目(12005096);湖南省自然科学基金面上项目(2022JJ30479)。

摘　　要：为研究堆芯换热系数不确定性对堆芯功率控制系统的影响,以小型压水堆为例,构建堆芯状态空间模型,结合PID控制器,建立堆芯功率控制系统,利用拉丁超立方方法进行参数抽样,开展不同功率水平下堆芯反应性阶跃扰动和堆芯冷却剂进口温度阶跃扰动的仿真,最后采用区间估计Bootstrap方法进行不确定性量化分析。结果表明:40%FP下堆芯换热系数的不确定性对堆芯功率控制系统的影响比100%FP下的更显著,在PID控制器的作用下,堆芯相对功率和冷却剂平均温度的不确定度均在0.1176%以内,堆芯换热系数不确定性对堆芯功率控制系统的影响是可接受的。To study the influence of the core heat transfer coefficient uncertainty on the core power control system of small pressurized water reactor,first of all,a core power control system was established with the state space model of the reactor core and the PID controller.Then,the sample size was determined and parameter sampling was performed with the Latin hypercubic method.Afterward,the dynamic simulations of reactivity step perturbation and core coolant inlet temperature step perturbation at different power levels were carried out.Finally,the interval estimation Bootstrap method was used for the uncertainty quantitative analysis.The result show that at 40%FP,the core heat transfer coefficient uncertainty affects more significantly than at 100%FP on the core power control system.Under the control of the PID controller,the uncertainty of the core relative power and the coolant average temperature are within 0.1176%,and the impact of the core heat transfer coefficient uncertainty on the core power control system is acceptable.

关 键 词：堆芯换热系数 区间估计Bootstrap法 不确定性 功率控制 

分 类 号：TL48[核科学技术—核技术及应用]