Development of three-dimensional thermal-hydraulic analysis code for steam generator with two-fluid model and porous media approach

被引：11
|
作者：
Lu, Daogang [1 ]
Wang, Yu [1 ]
Yuan, Bo [2 ]
Sui, Danting [1 ]
Zhang, Fan [3 ]
Guo, Chao [1 ]
Wang, Cong [1 ]
Zhang, Shuming [4 ]
机构：
[1] North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
[2] Changjiang Inst Survey Planning Design & Res, Wuhan 430010, Peoples R China
[3] Univ Tennessee, Knoxville, TN 37996 USA
[4] State Nucl Power Software Dev Ctr, Beijing 102209, Peoples R China
来源：
APPLIED THERMAL ENGINEERING | 2017年 / 116卷
关键词：
Steam generator; Two-fluid model; Porous media; Thermal-hydraulic analysis; TUBE HEAT-EXCHANGERS; NUMERICAL-SIMULATION; FLOW;
D O I：
10.1016/j.applthermaleng.2017.01.095
中图分类号：
O414.1 [热力学];
学科分类号：
摘要：
Steam generator (SG) is one of the major components in nuclear power plants, thus, it is crucial to analyze its thermal-hydraulic characteristics for the economical and safe operation. Various analytical codes have formulated for the research of the secondary side of SG. However, due to its complex geometry, the previous analytical codes have certain limitations in accurately predicting the thermal-hydraulic characteristics at secondary side. In this paper, a specialized code named THAC-SG (Thermal-hydraulic Analysis Code-Steam Generator) has been developed after summarizing main feature of widely-used steam generator three-dimensional thermal-hydraulics calculation codes. The finite volume method is used for the computation of two-phase flow and natural circulation at secondary side, and the complex structure was simulated by porous-media model. This paper takes the SG of Guangdong Daya Bay Nuclear Power Station (GNPS) as the verification model. The code can simulate the dynamically varying void fraction, pressure and temperature in the secondary side. The accuracy and reliability of this code has been validated and can be used for thermal-hydraulic analysis of steam generator under various operating conditions. (C) 2017 Elsevier Ltd. All rights reserved.
引用
收藏
页码：663 / 676
页数：14
相关论文
共 50 条
  • [1] Development of Three-dimensional Thermal-hydraulic Analysis Code HeTAF for Helical Coil Steam Generator
    Liu K.
    Wang M.
    Zhang J.
    Tian W.
    Qiu S.
    Su G.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2022, 56 (11): : 2272 - 2282
  • [2] Development and Application of Three-dimensional Nuclear Steam Generator Thermal-hydraulic Analysis Code STAF
    Tian W.
    Wang M.
    Zeng C.
    Qiu S.
    Su G.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2022, 56 (11): : 2239 - 2252
  • [3] Development of thermal-hydraulic analysis code of a helically coiled once-through steam generator based on two-fluid model
    Chen, Huandong
    Chen, Jiayue
    Zhang, Xiaoying
    ANNALS OF NUCLEAR ENERGY, 2019, 132 : 773 - 783
  • [4] DEVELOPMENT OF THERMAL-HYDRAULIC COMPUTER CODE FOR STEAM-GENERATOR
    HIRAO, Y
    NAKAMORI, N
    UKAI, O
    KAWANISHI, K
    TSUGE, A
    UENO, T
    KUSAKABE, T
    JSME INTERNATIONAL JOURNAL SERIES B-FLUIDS AND THERMAL ENGINEERING, 1993, 36 (03) : 456 - 463
  • [5] SCALING OF HORIZONTAL STEAM GENERATOR BASED ON THREE-DIMENSIONAL THERMAL-HYDRAULIC SIMULATIONS
    Lazarevic, Milos
    Stevanovic, Vladimir
    Petrovic, Milan M.
    Milivojevic, Sanja
    Ilic, Milica
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 11, ICONE31 2024, 2024,
  • [6] DEVELOPMENT OF A THERMAL-HYDRAULIC ANALYSIS CODE FOR HELICAL COILED ONCE THROUGH STEAM GENERATOR
    Huang, Jun
    Gou, Junli
    Ma, Haifu
    Fan, Jie
    Shan, Jianqiang
    PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 6B, 2018,
  • [7] Thermal-hydraulic design and analysis code development for steam generator of CFR600
    Sun, Peiwei
    Wang, Zi
    Zhang, Jianmin
    Su, Guanghui
    ANNALS OF NUCLEAR ENERGY, 2016, 90 : 256 - 263
  • [8] Thermal-hydraulic Code Development and Analysis of HTGR Helical Tube Supercritical Steam Generator
    Fan, Hongyi
    Li, Xiaowei
    Wu, Xinxin
    Sun, Libin
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2022, 56 (11): : 2343 - 2353
  • [9] Development of a two-fluid based thermal-hydraulic subchannel analysis code with high-resolution numerical method
    Gui, Minyang
    Tian, Wenxi
    Wu, Di
    Chen, Ronghua
    Wang, Mingjun
    Su, G. H.
    PROGRESS IN NUCLEAR ENERGY, 2021, 134
  • [10] Three-dimensional steady state thermal-hydraulic analysis of secondary side for CPR1000 steam generator
    China Nuclear Power Design Co. Ltd., Shenzhen
    518172, China
    不详
    100082, China
    Yuanzineng Kexue Jishu, 7 (1227-1231):
12345