Quantitative Research on Parameter Uncertainty of Helical Coil Once-Through Tube Steam Generator on the Small Pressurized Water Reactor

Liang Lehua; Wang Xuejian; Zeng Wenjie; Li Chuhao

doi:10.13832/j.jnpe.2023.03.0152

Volume 44 Issue 3

Jun. 2023

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2023 > 44(3): 152-159

Liang Lehua, Wang Xuejian, Zeng Wenjie, Li Chuhao. Quantitative Research on Parameter Uncertainty of Helical Coil Once-Through Tube Steam Generator on the Small Pressurized Water Reactor[J]. Nuclear Power Engineering, 2023, 44(3): 152-159. doi: 10.13832/j.jnpe.2023.03.0152

Citation:

Liang Lehua, Wang Xuejian, Zeng Wenjie, Li Chuhao. Quantitative Research on Parameter Uncertainty of Helical Coil Once-Through Tube Steam Generator on the Small Pressurized Water Reactor[J]. Nuclear Power Engineering, 2023, 44(3): 152-159. doi: 10.13832/j.jnpe.2023.03.0152

Citation:

Liang Lehua, Wang Xuejian, Zeng Wenjie, Li Chuhao. Quantitative Research on Parameter Uncertainty of Helical Coil Once-Through Tube Steam Generator on the Small Pressurized Water Reactor[J]. Nuclear Power Engineering, 2023, 44(3): 152-159. doi: 10.13832/j.jnpe.2023.03.0152

PDF( 10255 KB)

Quantitative Research on Parameter Uncertainty of Helical Coil Once-Through Tube Steam Generator on the Small Pressurized Water Reactor

doi: 10.13832/j.jnpe.2023.03.0152

1.
School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, China
2.
Department of Nuclear engineering design and Research, China Institute of Atomic Energy, Beijing, 102413, China

Received Date: 2022-07-26
Accepted Date: 2022-07-21
Rev Recd Date: 2022-08-27
Publish Date: 2023-06-15

Abstract

Abstract

To study the influence of parameter uncertainties of helical coil once-through tube steam generator (HCOTSG) on the operation of small pressurized water reactor, based on the establishment of the core power control system, the feed water control system of steam generator and the pressure and water level control system of pressurizer a quantitative platform for parameter uncertainties of HCOTSG on the small pressurized water reactor was developed. Taking the uncertainty quantification of inner and outer diameters of helical pipes as an example, the application research of the platform is carried out. The results show that the developed platform can well quantify the uncertainty of the primary system of small pressurized water reactor.
- Helical coil once-through tube steam generator,
- Inner and outer diameter of the helical tube,
- Uncertainty

FullText(HTML)

References(7)

References

[1]	袁媛,彭敏俊,夏庚磊,等. 螺旋管式直流蒸汽发生器热工水力分析模型[J]. 原子能科学技术,2014, 48(S1): 251-256.
[2]	赵孝,张震,杨星团,等. 小型模块式反应堆螺旋管蒸汽发生器设计和热工水力分析[J]. 原子能科学技术,2019, 53(12): 2361-2366. doi: 10.7538/yzk.2019.youxian.0452
[3]	WEI X Y, WU S F, WANG P F, et al. Study on the structure optimization and the operation scheme design of a double-tube once-through steam generator[J]. Nuclear Engineering and Technology, 2016, 48(4): 1022-1035. doi: 10.1016/j.net.2016.02.012
[4]	WANG P F, JIANG Q F, ZHANG J X, et al. A fuzzy fault accommodation method for nuclear power plants under actuator stuck faults[J]. Annals of Nuclear Energy, 2022, 165: 108674. doi: 10.1016/j.anucene.2021.108674
[5]	ISHII M, HIBIKI T. Thermo-fluid dynamics of two-phase flow[M]. 2nd ed. New York: Springer, 2011: 518.
[6]	闫寿军. 小型压水堆系统仿真与动态特性研究[D]. 西安: 西安交通大学, 2017.
[7]	LIU Y N, JIANG Q F, YANG C, et al. Uncertainty analysis of reactivity feedback coefficient for LFR core power control system during reactivity insertion accident[J]. Annals of Nuclear Energy, 2021, 160: 108401. doi: 10.1016/j.anucene.2021.108401