安全性和经济性满足较小功率用户需求的小型核反应堆为近年来的研究热点，一体化布置水冷反应堆为小型核反应堆的主要堆型之一。核反应堆控制棒驱动机构是反应堆最关键的安全设备，担负着反应堆的启动、功率调节及停堆等重要功能。该文给出一种应用于一体化布置水冷反应堆的内置式控制棒水压驱动技术，包括功率小于50 MW的A型和热功率50~300 MW的B型2种整体设计方案、部件组成、主要功能和性能等工程研究和应用。为一体化水堆提供了完整的内置式控制棒驱动线，包括其部件组成、联接结构、固定方式和功能；降低了反应堆高度；避免了弹棒事故，增强了反应堆安全性；使一体化布置反应堆更加紧凑、体积小、自然循环能力加强。
Abstract
In recent years, many researchers have focused on small nuclear reactors that provide good economics and safety characteristics for small users with the integrated water reactor as one of the main reactor types for small nuclear reactors. The control rod drive mechanism is a key component during reactor startup, power regulation and shutdown. This paper describes an in-vessel type control rod hydraulic drive mechanism for integrated water reactors, including the structure, the components, the main functions and the performance. Type A is designed for reactors with power levels less than 50 MW with type B for 50~300 MW reactors. This study provides a complete in-vessel type control rod drive line for integrated water reactors including the components, connecting structures, modes and functions that reduce the reactor height, prevent the control rod ejection accident and enhance the reactor safety to make the integrated water reactor more compact with natural circulation.
关键词
一体化水堆 /
内置式 /
控制棒 /
水压驱动机构
Key words
integrated water reactor /
in-vessel type /
control rod /
hydraulic drive mechanism
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参考文献
[1] 周培德, 侯斌, 陈晓亮, 等. 小型反应堆技术发展趋势[J]. 原子能科学技术, 2020, 54(Suppl.):218-225. ZHOU P D, HOU B, CHEN X L, et al. Development trend of small reactor technology[J]. Atomic Energy Science and Technology, 2020, 54(Suppl.):218-225. (in Chinese)
[2] KIN I G, BANG I C. Hydraulic control rod drive mechanism concept for passive in-core cooling system (pincs) in fully passive advanced nuclear power plant[J]. Experimental Thermal and Fluid Science, 2017, 85:266-278.
[3] ISHIDA T, IMAYOSHI S, YORITSUNE T, et al. Development of in-vessel type control rod drive mechanism for marine reactor[J]. Journal of Nuclear Science and Technology, 2001, 38(7):557-570.
[4] ZHENG Y H, BO H L, DONG D. Theoretical analysis of the working performance of the hydraulic control rod driving system in perturbation or inclination[J]. Nuclear Technology, 2007, 157(2):208-214.
[5] ZHENG Y H, BO H L, DONG D. The study on the hydraulic control rod driving system in cyclical swing[J]. Nuclear Engineering and Design, 2007, 237(1):100-106.
[6] BO H L, ZHENG Y H, ZHENG W X, et al. Study on step-up characteristic of hydraulic control rod driving system[J]. Nuclear Engineering and Design, 2002, 216(1-3):69-75.
[7] ZHENG Y H, BO H L, DONG D, et al. Experiment study on rod ejection accident of hydraulic control rod driving system[J]. Journal of Nuclear Science and Technology, 2001, 38(12):1133-1137.
[8] BO H L, ZHENG W X, DONG D. Studies on the performance of the hydraulic control rod drive for the NHR-200[J]. Nuclear Engineering and Design, 2000, 195(1):117-121.
[9] 陈济东. 大亚湾核电站系统及运行[M]. 北京:原子能出版社, 1998. CHEN J D. System and operation on Daya Bay nuclear power station[M]. Beijing:Atomic Energy Press, 1998. (in Chinese)
[10] 薄涵亮, 郑文祥, 王大中, 等. 核反应堆控制棒水压驱动技术[J]. 清华大学学报(自然科学版), 2005, 45(3):424-427. BO H L, ZHENG W X, WANG D Z, et al. Hydraulic control rod drive technology for nuclear reactors[J]. Journal of Tsinghua University (Science and Technology), 2005, 45(3):424-427. (in Chinese)
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