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

被引：0
|
作者：
Liang L. [1 ]
Wang X. [1 ]
Zeng W. [1 ,2 ]
Li C. [1 ]
机构：
[1] School of Nuclear Science and Technology, University of South China, Hunan, Hengyang
[2] Department of Nuclear engineering design and Research, China Institute of Atomic Energy, Beijing
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2023年 / 44卷 / 03期
关键词：
Helical coil once-through tube steam generator; Inner and outer diameter of the helical tube; Uncertainty;
D O I：
10.13832/j.jnpe.2023.03.0152
中图分类号：
学科分类号：
摘要：
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. © 2023 Yuan Zi Neng Chuban She. All rights reserved.
引用
收藏
页码：152 / 159
页数：7
相关论文
共 7 条
  • [1] 48, pp. 251-256, (2014)
  • [2] 53, 12, pp. 2361-2366, (2019)
  • [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, Nuclear Engineering and Technology, 48, 4, pp. 1022-1035, (2016)
  • [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, Annals of Nuclear Energy, 165, (2022)
  • [5] ISHII M, HIBIKI T., Thermo-fluid dynamics of two-phase flow, (2011)
  • [6] (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, Annals of Nuclear Energy, 160, (2021)
1