THERMAL SCIENCE
International Scientific Journal
Find this paper on
PARAMETRIC INVESTIGATION ON THE MEASUREMENT ACCURACY OF DIFFERENTIAL PRESSURE SYSTEM FOR NUCLEAR POWER PLANT STEAM GENERATOR
ABSTRACT
Steam generator is an important equipment of nuclear power unit, and its flow rate is directly related to the operating power of the unit. Accurate flow measurement and monitoring is an effective prerequisite to ensure stable and long-term operation of the unit. However, when the pressure taking system is used to measure the steam-flow rate, the phenomenon that the flow indication number is abnormal but the actual flow rate does not change occasionally often occurs, which affects the normal production operation. Based on the principle of differential pressure method, this study studied the influence of flow resistance and flow characteristics of waveform plate steam separator, an important part of steam generator, on flow measurement, and completed the analysis of waveform plate flow field and the establishment of benchmark model through numerical simulation. The uncertainty quantization method based on Morris One at A Time (MOAT) was used to analyze the sensitivity of the deviation factors affecting the accuracy of flow measurement at the waveform plate. By comparing MOAT mean and MOAT standard deviation, it is found that the assembly inclination angle of the corrugated plate is the most important factor affecting the measurement accuracy of flow rate, and should be the key check item during the maintenance of steam generator.
KEYWORDS
steam generator, Pressure Taking Measurement System, Corrugated Plate Separator, computational fluid dynamics, Quantization of Uncertainty
PAPER SUBMITTED: 2025-04-26
PAPER REVISED: 2025-06-18
PAPER ACCEPTED: 2025-06-18
PUBLISHED ONLINE: 2025-08-02
DOI REFERENCE: https://doi.org/10.2298/TSCI250426144Z
CITATION EXPORT: view in browser or download as text file
[1] Shen, Y., Study on Flushing Technology for Tube Sheet on the Secondary Side of Nuclear Power Steam Generator Based on Numerical Simulation, Cleaning World, 40 (2024), 3, pp. 63-66+69
[2] Liu, F., Discussion on Welding Technology for In-Service Replacement of Nuclear Power Plant Steam Generator, Welding Technology, 53 (2024), 4, pp. 63-67
[3] Zeng, C. J., et al., Development of a Full-Scale Steam-Water Separation Device Model for Steam Generators, Atomic Energy Science and Technology, 56 (2022), 11, pp. 2253-2261
[4] Xu, D. H., et al., Thermal State Test and Numerical Study of a New Conical Swirl-Vane Steam-Water Separator, Journal of Shanghai Jiao Tong University, 55 (2021), 9, pp. 1087-1094
[5] Huang, Z., et al., Study on Separation Efficiency Model of Swirl-Vane Steam-Water Separator, Proceedings, Annual Meeting of the Chinese Nuclear Society (eds. China Nuclear Power Research and Design Institute), Weihai, China, Vol. 3, 2017, p. 7
[6] Li, J., Theoretical and Experimental Study on Corrugated Plate Steam-Water Separator, Ph. D. thesis, Huazhong University of Science and Technology, Wuhan, China, 2007
[7] Ortner, B., et al., Analysis of the Shear-Driven Flow in a Scale Model of a Phase Separator: Validation of a Coupled CFD Approach Using Experimental Data from a Physical Model, Int. J. Multiphase Flow, 177 (2024), 104852
[8] Liu, Z. W., Bo, H. L., Three-Dimensional Euler Grid Approximation Method for Multi-Droplet Motions in the Steam-Water Separator, Case Studies in Thermal Engineering, 51 (2023), 103545
[9] Xu, H. C., et al., Stress Calculation and Analysis of a 600MW Supercritical Boiler's Steam-Water Separator, E3S Web of Conferences, 261 (2021), 01050
[10] Kvascev, G. S., Zahirovic, D. M., Water Level Control in the Thermal Power Plant Steam Separator Based on New PID Tuning Method for Integrating Processes, Energies, 15 (2022), 17, 6310
[11] Shi, Z. L., et al., Flow Field Analysis and Structural Optimization of Steam Generator Restrictor, Chemical Equipment Technology, 39 (2018), 1, pp. 27-30
[12] Yang, X. L., et al., Influence of Steam Restrictor Structure on Flow Resistance and Flow Field Details, Nuclear Power Engineering, 36 (2015), 4, pp. 23-27
© 2026 Society of Thermal Engineers of Serbia. Published by the Vinča Institute of Nuclear Sciences, National Institute of the Republic of Serbia, Belgrade, Serbia. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution-NonCommercial-NoDerivs 4.0 International licence


