基于滑模观测器的APR1400可溶硼预测控制负载跟踪过程中氙估计研究

IF 2.6 4区 综合性期刊 Q2 MULTIDISCIPLINARY SCIENCES
Husam Khalefih, Yonghee Kim
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引用次数: 0

摘要

在核反应堆的日常负荷跟随操作(DLFOs)中,氙浓度随功率水平而变化,需要通过稀释或硼化来调整可溶性硼浓度。由于氙不能在反应器内直接测量,本研究引入了滑模观测器(SMO)来估计DLFO期间的氙浓度。根据这些估计,使用控制算法(Mode-K +)计算必要的硼浓度调整,该算法集成了反应堆化学控制系统、氙和硼值的数据。这项研究的重点是APR1400反应堆的初始循环,并证明了估计的氙浓度与康德内部3D时间依赖氙模型得出的参考值之间的高度准确性。SMO与负荷跟随运行控制算法的集成是一项重大进步,它为反应堆操作员提供了精确的硼调整信息。这种精度最大限度地减少了不必要的控制棒移动,从而降低了轴向或径向功率峰值的风险,这是维持反应堆稳定性和安全性的关键因素。此外,该方法通过精确定时和控制引入系统的去矿化水的体积,优化了硼稀释过程。这不仅确保了负载跟踪操作的有效执行,而且大大减少了产生的液体放射性废物的体积。分析采用两步程序进行:通过Serpent 2.2.0连续能量蒙特卡罗代码进行横断面评估,然后使用KANT进行全核计算以生成集总参数。该方法为提高核反应堆在负荷跟踪情况下运行的安全性和效率提供了一种新颖的解决方案。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
A Study on Xenon Estimation During Load-Follow Operation Using Sliding Mode Observer in APR1400 for A Predictive Soluble Boron Control

During daily load-follow operations (DLFOs) in nuclear reactors, xenon concentration varies with power level, necessitating adjustments to the soluble boron concentration via dilution or boration. Since xenon cannot be directly measured within the reactor, this study introduces the use of a sliding mode observer (SMO) to estimate xenon concentration on the fly during the DLFO. Based on these estimates, the necessary boron concentration adjustments are calculated using a control algorithm (Mode-K +) that integrates data on the reactor’s chemical control system, xenon, and boron worth. This study focuses on the APR1400 reactor’s initial cycle and demonstrates a high degree of accuracy between the estimated xenon concentrations and reference values derived from KANT’s in-house 3D time-dependent xenon model. The integration of the SMO with the load-follow operation control algorithm represents a significant advancement by providing reactor operators with precise boron adjustment information. This precision minimizes unnecessary control rod movements, thereby reducing the risk of axial or radial power peaking, a critical factor for maintaining reactor stability and safety. Additionally, this approach optimizes the boron dilution process by accurately timing and controlling the volume of demineralized water introduced into the system. This not only ensures the effective execution of load-follow operations but also significantly reduces the volume of liquid radioactive waste produced. The analysis was conducted using a two-step procedure: cross-sectional evaluation via the Serpent 2.2.0 continuous energy Monte Carlo code, followed by whole-core calculations to generate lumped parameters using KANT. This methodology offers a robust and novel solution for enhancing the safety and efficiency of nuclear reactor operations during load-follow scenarios.

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来源期刊
Arabian Journal for Science and Engineering
Arabian Journal for Science and Engineering MULTIDISCIPLINARY SCIENCES-
CiteScore
5.70
自引率
3.40%
发文量
993
期刊介绍: King Fahd University of Petroleum & Minerals (KFUPM) partnered with Springer to publish the Arabian Journal for Science and Engineering (AJSE). AJSE, which has been published by KFUPM since 1975, is a recognized national, regional and international journal that provides a great opportunity for the dissemination of research advances from the Kingdom of Saudi Arabia, MENA and the world.
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