基于ACP1000核电站一次回路的分数阶神经瞬态建模

A. H. Malik, A. Memon, Feroza Arshad
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引用次数: 1

摘要

核电站的一次回路是中国先进压水堆(ACP1000)中最先进、最精密的回路。主电路由技术最先进的核系统和控制器组成。在本研究工作中,对ACP1000核电站一次回路(CLPC)的闭环动力学进行了识别。闭环动力学是由高度非线性耦合的七控制系统组成的。涡轮机功率、稳压器温度、冷段温度、热段温度、冷却剂平均温度和给水流量是选定的感兴趣参数作为输入,而中子功率、反应堆冷却剂压力、稳压器液位、蒸汽发生器压力、蒸汽发生器液位和蒸汽发生器流量作为输出。因此,配置了闭环多输入多输出(MIMO)。利用LabVIEW开发的最先进的新型分数阶神经网络(FO-ANN)工具,对ACP1000主电路的面向控制的闭环动力学进行了估计。利用分数阶反向传播(FO-BP)算法对CLPC的FO-ANN(FO-ANN-CLPC)参数进行了优化。在瞬态条件下对FO-ANN-CLPC的性能进行了测试和验证,所提出的模型以最小化误差函数预测了所需的反应堆功率。通过对规定的涡轮机负载功率从20%增加到100%的瞬态的动态模拟,评估了所提出的闭环模型的鲁棒性能,并根据反应堆功率进行了验证,观察和分析了各种热工水力学参数的行为。
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Fractional Order Neural Transient Modeling of Primary Circuit of ACP1000 Based Nuclear Power Plant in LabVIEW
The primary circuit of the nuclear power plant is the most advanced and sophisticated loop of the Advanced Chinese Pressurized Water Reactor (ACP1000). The primary circuit is composed of most technologically advanced nuclear systems and controllers. In this research work, closed loop dynamics of primary circuit (CLPC) of ACP1000 based nuclear power plant is identified. The closed loop dynamics is comprised of highly nonlinear coupled sevencontrol systems. The turbine power, pressurizer temperature, cold leg temperature, hot leg temperature, coolant average temperature and feed water flow are the selected parameters of interest as inputs while neutron power, reactor coolant pressure, pressurizer level, steam generator pressure, steam generator level and steam generator flow as outputs. Therefore, a closed loop multi-input multi-out (MIMO) is configured. The control oriented closed loop dynamics of the primary circuit of ACP1000 is estimated by state-of-the-art novel fractional order neural network (FO-ANN) tool developed in LabVIEW. The parameters of FO-ANN of CLPC (FO-ANN-CLPC) are optimized using fractional order backpropagation (FO-BP) algorithm. The performance of FO-ANN-CLPC is tested and validated in transient conditions and the proposed model predicted the desired reactor power with minimizing error function. The robust performance of the proposed closed loop model is evaluated by dynamic simulation for a prescribed turbine load power increase transient from 20 % to 100 % and validated against reactor power and behaviour of various thermal hydraulics parameters are observed and analyzed.
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来源期刊
Proceedings of the Pakistan Academy of Sciences: Part A
Proceedings of the Pakistan Academy of Sciences: Part A Computer Science-Computer Science (all)
CiteScore
0.70
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0.00%
发文量
15
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