EN核能水电联产系统的变负荷动态特性与灵活运行控制策略优化研究
Research on Dynamic Characteristics and Flexible Operation Control Strategy Optimization of Nuclear Power and Water Cogeneration System
- 动力工程学报 2025年45卷第4期 页码：582-591
- 作者机构：
1. 西安交通大学 绿色氢电全国重点实验室,陕西,西安,710049
2. 华南理工大学 电力学院,广东,广州,510641
3. 中国核电工程有限公司,北京,100840
- 作者简介：
[ "吴青阳(1996—),男,陕西榆林人,博士研究生,主要从事核能水电联产方面的研究" ]
[ "严俊杰(通信作者),男,教授,博士,E-mail:yanjj@mail.xjtu.edu.cn" ]
- 基金信息：国家自然科学基金资助项目(52276016);中核集团领创科研资助项目
DOI：10.19805/j.cnki.jcspe.2025.240261
中图分类号： TM623-
网络出版：2025-04-28，
纸质出版：2025
- 稿件说明：
移动端阅览
吴青阳,李根,刘明,韩小渠,张玉峰,严俊杰. 核能水电联产系统的变负荷动态特性与灵活运行控制策略优化研究动力工程学报, 2025, 45(4): 582-591 https://doi.
org/10.19805/j.cnki.jcspe.2025.240261
吴青阳,李根,刘明,韩小渠,张玉峰,严俊杰. 核能水电联产系统的变负荷动态特性与灵活运行控制策略优化研究动力工程学报, 2025, 45(4): 582-591 https://doi. DOI： 10.19805/j.cnki.jcspe.2025.240261.
org/10.19805/j.cnki.jcspe.2025.240261 DOI：
摘要
为消纳大规模并网发电的可再生能源
核电机组参与调峰成为大势所趋
但频繁调节反应堆功率影响核电机组的运行安全性和经济性。提出通过水电联产和功率控制策略优化提升核电机组的运行灵活性。结合案例核电机组
动态模拟了1%~5%FP/min(FP
额定负荷)不同变负荷速率的变负荷性能
定量分析了变负荷过程中燃料棒中心温度变化偏差。结果表明:所提出的耦合控制策略可实现核电机组在65%FP到90%FP的变负荷区间能灵活调节
提高了核能水电联产集成系统的运行灵活性
且在变负荷过程中可维持反应堆满负荷运行
提高了核能利用率
同时减少了控制棒的频繁移动
提升了反应堆的运行安全性;耦合控制策略相比原控制策略
变负荷过程燃料棒中心温度降低了41.24%~45.28%
降低了包壳承受的交变应力
进而延长了燃料棒包壳寿命以及提升了核电机组的运行安全性和稳定性。
Abstract
To accommodate the large scale renewable power combined to the grid
participation of nuclear power units in peak shaving becomes a trend. However
frequent adjustment of reactor power affects the operational safety and economy of nuclear power units. Power and water cogeneration and power control strategy optimization were proposed to enhance the operational flexibility of nuclear power units. The variable load performance under different variable load rates of 1%-5%FP/min was dynamically simulated in combination with the case nuclear power unit. In addition
the center temperature deviation of the fuel rods during the variable load process was quantitatively analyzed. Results show that the proposed coupling power control strategy can achieve flexible adjustment in the variable load range of 65%FP to 90%FP
which improves the operational flexibility of the power and water cogeneration integrated system. Furthermore
the full load operation of the reactor is maintained during the variable load process
which reduces the frequent movement of the control rods and improves the operational safety of the reactor. Compared to the original power control strategy
the coupling power control strategy reduces the range of fuel rod center temperature deviation by 41.24% to 45.28% during variable load process
reducing the alternating stress experienced by the fuel rod cladding
thereby improving the life of fuel rod cladding and the safe and stable operation of nuclear power units.
关键词
Keywords
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