Research on Control Strategy of the Coolant System for Low-Temperature Heating Reactor

Jiang Qingfeng; Hong Hao; Lyu Hong; Wang Pengfei

doi:10.13832/j.jnpe.2024.090030

Volume 46 Issue 5

Oct. 2025

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2025 > 46(5): 171-179

Jiang Qingfeng, Hong Hao, Lyu Hong, Wang Pengfei. Research on Control Strategy of the Coolant System for Low-Temperature Heating Reactor[J]. Nuclear Power Engineering, 2025, 46(5): 171-179. doi: 10.13832/j.jnpe.2024.090030

Citation:

Jiang Qingfeng, Hong Hao, Lyu Hong, Wang Pengfei. Research on Control Strategy of the Coolant System for Low-Temperature Heating Reactor[J]. Nuclear Power Engineering, 2025, 46(5): 171-179. doi: 10.13832/j.jnpe.2024.090030

Citation:

PDF( 10947 KB)

Research on Control Strategy of the Coolant System for Low-Temperature Heating Reactor

doi: 10.13832/j.jnpe.2024.090030

1.
School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049, China
2.
State Key Laboratory of Nuclear Power Safety Technology and Equipment, China Nuclear Power Engineering Co., Ltd., Shenzhen, Guangdong, 518116, China

Received Date: 2024-09-10
Rev Recd Date: 2024-10-24

Available Online: 2025-10-15

Publish Date: 2025-10-15

Abstract

Abstract

To ensure the operation safety of low-temperature heating reactors, it is crucial to study reactor power control strategies that meet their operational requirements. To this end, this study takes the low-temperature heating reactor coolant system as the research object and proposes two control strategies: a dual-feedback control strategy and a cascade control strategy. Their respective effects on the coupled control of reactor power and core coolant outlet temperature are investigated. The simulation results show that both control strategies can effectively control the low-temperature heating reactor coolant system under step and linear load change conditions. Under the cascade control strategy, the coolant outlet temperature is the main controlled variable, whose change magnitude is small in the load change conditions, but the settling time of reactor power is prolonged. Therefore, the cascade control strategy is more suitable for the linear load change conditions. Under the double-feedback control strategy, the reactor power control channel and the temperature control channel are in a parallel configuration, allowing both control performances to be taken into account. Therefore, the double-feedback control strategy is more suitable for the step load change conditions. This study can provide a reference for the development and optimization of low-temperature heating reactor coolant system control strategy.
- Low-temperature heating reactor,
- Coolant system,
- Double-feedback control strategy,
- Cascade control strategy

FullText(HTML)

References(15)

References

[1]	LI Y, BU F J, GAO J K, et al. Optimal dispatch of low-carbon integrated energy system considering nuclear heating and carbon trading[J]. Journal of Cleaner Production, 2022, 378: 134540. doi: 10.1016/j.jclepro.2022.134540
[2]	WANG D Z, MA C W, DONG D, et al. Chinese nuclear heating test reactor and demonstration plant[J]. Nuclear Engineering and Design, 1992, 136(1): 91-98.
[3]	ZHANG Y X, CHENG H P, LIU X M, et al. Swimming pool-type low-temperature heating reactor: recent progress in research and application[J]. Energy Procedia, 2017, 127: 425-431. doi: 10.1016/j.egypro.2017.08.110
[4]	郝文涛, 张亚军. 低温供热堆研究进展[J]. 中国核电, 2019, 12(5): 518-521.
[5]	张乐, 段天英, 贾玉文. 低温堆负荷跟踪控制研究[J]. 节能技术, 2022, 40(4): 367-373. doi: 10.3969/j.issn.1002-6339.2022.04.014
[6]	蔡宝玲, 马晓珑, 孟强, 等. 高温气冷堆核电机组一次调频控制策略研究[J]. 热力发电, 2022, 51(2): 71-77.
[7]	WAN J S, WANG P F, WU S F, et al. Controller design and optimization of reactor power control system for ASPWR[J]. Progress in Nuclear Energy, 2017, 100: 233-244. doi: 10.1016/j.pnucene.2017.06.006
[8]	肖凯, 廖龙涛, 周科, 等. 多堆多机核动力装置控制方案建模及仿真研究[J]. 南华大学学报: 自然科学版, 2017, 31(3): 13-20.
[9]	NSA Division. RELAP5/MOD3.3 code manual, Volume 4: Models and correlations[R]. USA: Information Systems Laboratories, Inc., 2001: 118-163, 517-518.
[10]	EL HEFNI B, BOUSKELA D. Modeling and simulation of thermal power plants with ThermoSysPro[M]. Cham: Springer, 2019: 217-220.
[11]	于平安, 朱瑞安, 喻真烷, 等. 核反应堆热工分析[M]. 第三版. 上海: 上海交通大学出版社, 2002.
[12]	MA X Z, XIAO X, JIA H J, et al. Experimental research on steam condensation in presence of non-condensable gas under high pressure[J]. Annals of Nuclear Energy, 2021, 158: 108282. doi: 10.1016/j.anucene.2021.108282
[13]	WILSON J F, GRENDA R J, PATTERSON J F. The velocity of rising steam in a bubbling two-phase mixture[J]. Transactions of the American Nuclear Society, 1962, 5: 151-152.
[14]	MIN BAEK S, CHEON NO H, PARK I Y. A nonequilibrium three-region model for transient analysis of pressurized water reactor pressurizer[J]. Nuclear Technology, 1986, 74(3): 260-266. doi: 10.13182/NT86-A33828
[15]	WU S F, MA X L, LIU J F, et al. A load following control strategy for Chinese Modular High-Temperature Gas-Cooled Reactor HTR-PM[J]. Energy, 2023, 263: 125459. doi: 10.1016/j.energy.2022.125459