Failure Analysis of Once-Through Steam Generator (OTSG) Tube

被引:1
|
作者
Tina, Wahida [1 ]
Donaldson, Elizabeth [1 ]
Dickinson, Thomas E. [2 ]
Schmidt, William Hal [3 ]
机构
[1] Department of Asset Management, Lansing Board of Water and Light, 830 E. Hazel, Lansing,MI,48912, United States
[2] REO Town Plant, Peffley Chiller Plant, Lansing Board of Water and Light, 1201 S Washington Ave, Lansing,MI,48910, United States
[3] Department of Project Engineering, Lansing Board of Water and Light, 1201 S Washington Ave, Lansing,MI,48910, United States
来源
关键词
Descaling - Energy dispersive X ray analysis - Failure (mechanical) - Flow of gases - Heat exchangers - Heat transfer - Heat treatment - Nickel compounds - Optical emission spectroscopy - Scanning electron microscopy - Steam - Steam generators - Stress corrosion cracking - Thermoelectric power plants - Tubing - X ray diffraction analysis;
D O I
10.1115/1.4062769
中图分类号
学科分类号
摘要
The once-through steam generator (OTSG) produces superheated steam using purified feed water. The plant-specific water quality, steam quality, high temperature, and pressure operations lead to the leakage of the OTSG tubes with economic, safety, and environmental consequences. Tube leakage is one of the most frequent causes of OTSG tube failure. A leaking tube was discovered within the OTSG unit of the 110 MW cogeneration plant. The failed section of the tube was removed from the steam generator. Several metallurgical examinations of this tube segment were performed to identify the failure mode and cause. A portion of the tube was analyzed using optical emission spectroscopy (OES) to determine the alloy composition. The results confirmed that the tubing was fabricated from a material consistent with chemical specifications for ASME Specification SB 407 Inconel Alloy 800 (UNS N08800). Glass bead blasting was used to determine the deposit-weight-density (DWD). The DWD value was a maximum of 5.1 g/ft2. The maximum internal deposit thickness was 0.002 in. No evidence of overheating was observed. Scanning electron microscopeenergy-dispersive x-ray analysis (SEM-EDXA) was used to determine the elemental composition of the internal deposits. The results indicated that the internal gray deposits primarily comprised iron, chromium, and nickel compounds. There were also fewer amounts of sodium, silicon, aluminum, potassium, and calcium species. The subject tube failure involved a through-wall crack that occurred as stress corrosion cracking (SCC). Additions of caustic solution used in OTSG water treatment practices potentially induced corrosive substances into the tube. Copyright © 2023 by ASME.
引用
收藏
相关论文
共 50 条
  • [1] Failure Analysis of Once-Through Steam Generator (OTSG) External Piping Welds
    Nitin Saini
    Yajing Wang
    Leijun Li
    Journal of Failure Analysis and Prevention, 2022, 22 : 1180 - 1195
  • [2] Failure Analysis of Once-Through Steam Generator (OTSG) External Piping Welds
    Saini, Nitin
    Wang, Yajing
    Li, Leijun
    JOURNAL OF FAILURE ANALYSIS AND PREVENTION, 2022, 22 (03) : 1180 - 1195
  • [3] Editorial: Thermal-hydraulics in once-through steam generator (OTSG) for nuclear reactors
    Zhang, Luteng
    Sun, Yuze
    Duan, Xiongbo
    Ding, Wei
    FRONTIERS IN ENERGY RESEARCH, 2024, 12
  • [4] Analysis of flow instabilities for once-through steam generator
    State Key Laboratory of Multiphase Flow, Xi'an Jiaotong University, Xi'an 710049, China
    不详
    Hedongli Gongcheng, 2008, 5 (43-47):
  • [5] Inner tube optimization of double-tube once-through steam generator
    Wei, Xinyu
    Dai, Chunhui
    Wang, Li
    Zhao, Fuyu
    INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2013, 59 : 93 - 102
  • [6] NUCLEAR ONCE-THROUGH STEAM GENERATOR
    MCDONALD, BN
    JOHNSON, LE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1970, : 19 - &
  • [7] Dynamic simulation of once-through steam generator with concentric annuli tube
    Zhu Jingyan
    Guo Yun
    Zhang Zhijian
    ANNALS OF NUCLEAR ENERGY, 2012, 50 : 185 - 198
  • [8] Study on flow instability in annular tube once-through steam generator
    Wu, Ge-Ping
    Qiu, Sui-Zheng
    Su, Guang-Hui
    Jia, Dou-Nan
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2007, 41 (03): : 325 - 330
  • [9] Performance Analysis and Tube Inlet Orifice Length Evaluation of a Once-Through Steam Generator
    Han, Hun Sik
    Kang, Han-Ok
    Yoon, Juhyeon
    Kim, Young In
    Bae, Youngmin
    Kim, Sang Ji
    XII INTERNATIONAL CONFERENCE ON COMPUTATIONAL HEAT, MASS AND MOMENTUM TRANSFER (ICCHMT 2019), 2019, 128
  • [10] Analysis of Density Wave Oscillations in Helically Coiled Tube Once-Through Steam Generator
    Hao, Junwei
    Zhang, Yaoli
    Zheng, Jianxiang
    Zhou, Zhiwei
    Sheng, Xuanyu
    Hong, Gang
    Ye, Kai
    Li, Ning
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2016, 2016