Critical heat flux prediction using genetic programming for water flow in vertical round tubes

被引:16
|
作者
Lee, DG
Kim, HG
Baek, WP
Chang, SH
机构
[1] Department of Nuclear Engineering, Korea Adv. Inst. Sci. and Technol., Yusong-gu, Taejon, 305-701
关键词
D O I
10.1016/S0735-1933(97)00078-X
中图分类号
O414.1 [热力学];
学科分类号
摘要
The genetic programming method is used to develop critical heat flux (CHF) correlations for upward water flow in vertical round tubes under low pressure and low flow conditions. The genetic programming, as a symbolic regression tool, finds both the functional form and fitting coefficients of a correlation without any initial assumptions. Inlet and local condition type correlations are developed based on 414 and 314 CHI: data from KAIST CHF data bank, respectively. The inlet condition type correlation shows the rms error of 15.2% and the local condition type one shows the rms errors of 32.7% and 13.2% by the direct substitution method and the heat balance method, respectively. Prediction errors are smaller than or comparable to those for other existing correlations. (C) 1997 Elsevier Science Ltd.
引用
收藏
页码:919 / 929
页数:11
相关论文
共 50 条
  • [21] PREDICTION OF THE CRITICAL HEAT FLUX IN SUBCOOLED FLOW BOILING IN ROUND TUBE USING AN IMPROVED MECHANISTIC MODEL
    Yu Na
    Zhang Yu
    PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 4 PTS A AND B, 2011, : 873 - 880
  • [22] Prediction of the critical heat flux for saturated upward flow boiling water in vertical narrow rectangular channels
    Choi, Gil Sik
    Chang, Soon Heung
    JeongDepartment, Yong Hoon
    NUCLEAR ENGINEERING AND DESIGN, 2016, 303 : 1 - 16
  • [23] Critical heat flux prediction model for low quality flow boiling of water in vertical circular tube
    Pan, Jie
    Li, Ran
    Yang, Dong
    Wu, Gang
    INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2016, 99 : 243 - 251
  • [24] Critical heat flux prediction for water boiling in vertical tubes of a steam generator (vol 44, pg 179, 2005)
    Gallegos-Muñoz, A
    Payan-Rodriguez, LA
    Porras-Loaiza, GL
    Picon-Nuñez, M
    INTERNATIONAL JOURNAL OF THERMAL SCIENCES, 2005, 44 (07) : 609 - 609
  • [25] Critical heat flux for downward flows in vertical round pipes
    Hirose, Yoshiyasu
    Sibamoto, Yasuteru
    Hibiki, Takashi
    PROGRESS IN NUCLEAR ENERGY, 2024, 168
  • [26] The effect of vibration on critical heat flux in a vertical round tube
    Lee, YH
    Chang, SH
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2003, 40 (10) : 734 - 743
  • [27] Prediction of critical heat flux in vertical tube under flow oscillation condition
    Zhao, Da-Wei
    Su, Guang-Hui
    Qiu, Sui-Zheng
    Hedongli Gongcheng/Nuclear Power Engineering, 2010, 31 (03): : 36 - 39
  • [28] The critical mass flux for positive flow characteristic of heated tubes in the vertical water wall
    Tang, Guoli
    Li, Zhouhang
    Lyu, Junfu
    Wu, Yuxin
    Gu, Junping
    Liu, Qing
    APPLIED THERMAL ENGINEERING, 2019, 153 : 29 - 38
  • [29] Comparison of Standalone and Hybrid Machine Learning Models for Prediction of Critical Heat Flux in Vertical Tubes
    Khalid, Rehan Zubair
    Ullah, Atta
    Khan, Asifullah
    Khan, Afrasyab
    Inayat, Mansoor Hameed
    ENERGIES, 2023, 16 (07)
  • [30] Analysis of the critical heat flux in round vertical tubes under low pressure and flow oscillation conditions. Applications of artificial neural network
    Su, GH
    Morita, K
    Fukuda, K
    Pidduck, M
    Dounan, J
    Miettinen, J
    NUCLEAR ENGINEERING AND DESIGN, 2003, 220 (01) : 17 - 35