In-vessel control rod hydraulic drive mechanism for integrated water reactors

doi:10.16511/j.cnki.qhdxxb.2021.25.013

Download: PDF(12818 KB) HTML
Export: BibTeX | EndNote | Reference Manager | ProCite | RefWorks

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.

Keywords integrated water reactor in-vessel type control rod hydraulic drive mechanism

Issue Date: 16 April 2021

	Service

	E-mail this article
	E-mail Alert
	RSS
	Articles by authors

	BO Hanliang
	WANG Dazhong
	ZHANG Zuoyi
	JIANG Shengyao
	ZHANG Yajun
	QIN Benke
	ZHAO Chenru
	LIU Qianfeng
	WANG Jinhai

Cite this article:

BO Hanliang,WANG Dazhong,ZHANG Zuoyi, et al. In-vessel control rod hydraulic drive mechanism for integrated water reactors[J]. Journal of Tsinghua University(Science and Technology), 2021, 61(4): 338-349.

URL:

http://jst.tsinghuajournals.com/EN/10.16511/j.cnki.qhdxxb.2021.25.013 OR http://jst.tsinghuajournals.com/EN/Y2021/V61/I4/338

[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)