Experimental and Numerical Study on Thermal-hydraulics of Helical-coiled Once-through Steam Generator of Small Modular Pressurized Water Reactor

被引：0

作者：

Liu M. ^{[1
]}

Liu L. ^{[1
]}

Chao M. ^{[2
]}

Zhang W. ^{[2
]}

Xiao Y. ^{[1
]}

Gu H. ^{[1
]}

机构：

[1] School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai

[2] Shanghai Nuclear Engineering Research and Design Institute Co.Ltd., Shanghai

来源：

Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2022年 / 56卷 / 11期

关键词：

flow instability; heat transfer; helical-coiled once-through steam generator; thermal-hydraulics;

D O I：

10.7538/yzk.2022.youxian.0579

中图分类号：

学科分类号：

摘要：

The helical-coiled once-through steam generator (H-OTSG) is widely used in small modular reactors due to its compactness and higher heat transfer efficiency. In this study, an experimental and numerical simulation study of the thermal-hydraulics characteristics of H-OTSG under different thermal power conditions was carried out, and the experimental results were used to verify the one-dimensional system code SGTH-1D. The configuration consists of 85 helically coiled tubes divided into ten layers according to the coil diameter. Both steady-state experiments and flow instability experiments were conducted under thermal power condition ranging from 0 ?6 MW to 2 ?3 MW. Firstly, the steady-state experimental results show the difference between the shell-side inlet temperature and the tube-side outlet temperature increases with thermal power, which is due to the decreasing of the heat transfer capacity of the H-OTSG. Sensitivity analysis of the system parameters shows that the shell-side pressure has little effect on the average heat transfer coefficient. And the average heat transfer coefficient also is insensitive to tube-side pressure and shell-side inlet temperature under low thermal power conditions. However, under low thermal power conditions, the average heat transfer coefficient increases with the decrease of the tube-side pressure and the increases of the shell-side inlet temperature. Secondly, the flow instability experimental results show that the increase of the thermal power can stabilize the H-OTSG and decrease the inlet throttling of the flow instability thresholds because the length of the subcooled single-phase region increases with the thermal power. The sensitivity analysis of the system parameters shows that the increase of the tube-side pressure and the decrease of the shell-side inlet temperature are beneficial to the stability of the system. The influence of the shell-side parameters on the flow instability threshold is weaker than that of the tube-side parameters. Finally, a numerical study on the thermal-hydraulics characteristics of the configuration was carried out in the present study. By comparing the experimental data with the numerical simulation results of the SGTH-1D code, the accuracy of the SGTH-1D code in predicting the steady-state heat transfer characteristics and flow instability of configuration was verified. The SGTH-1D code can accurately predict the heat transfer rate of the H-OTSG under various thermal power conditions, and the prediction errors of shell-side and tube-side outlet temperatures are within ±1 ℃. The numerical results of flow instability characteristics of the SGTH-1D code are conservative at low thermal power condition, and the error of numerical results is within ±20% when the thermal power is larger than 1.2 MW. © 2022 Atomic Energy Press. All rights reserved.

引用

页码：2327 / 2333

页数：6

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