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首页> 外文期刊>Annals of nuclear energy >Uncertainty analysis of reactivity feedback coefficient for LFR core power control system during reactivity insertion accident
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Uncertainty analysis of reactivity feedback coefficient for LFR core power control system during reactivity insertion accident

机译:反应性插入事故中LFR核心电力控制系统反应性反馈系数的不确定性分析

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摘要

To study the influence of the reactivity feedback coefficient uncertainty on reactor core power control system, taking a lead-cooled fast reactor as the object, the core power control system with a BP neural network PID controller is designed. Drawing the input samples with Latin hypercube sampling method, the uncertainty quantitative analysis consists of the Chebyshev inequality and relative standard deviation calculation. Based on the method in this paper, the dynamic simulation of reactor core is performed. The results show that the uncertainties of the system output control performance parameters are less than 1% when introducing 50pcm and 100 pcm step reactivity. The uncertainty of the system output parameters changes and returns to zero with the action of the controller. (C) 2021 Published by Elsevier Ltd.
机译:为了研究反应性反馈系数不确定性对反应堆核心功率控制系统的影响,采用铅冷冷的快电抗器作为对象,设计了具有BP神经网络PID控制器的核心电力控制系统。 用拉丁超级采样方法绘制输入样本,不确定性定量分析包括Chebyshev不等式和相对标准偏差计算。 基于本文的方法,执行反应堆核的动态模拟。 结果表明,在引入50pcm和100pcm步骤反应性时,系统输出控制性能参数的不确定性小于1%。 系统输出参数的不确定性随着控制器的动作而更改并返回为零。 (c)2021由elestvier有限公司出版

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