Evaluation of interchannel exchange models with a subchannel analysis code

被引：0
|
作者：
Yoo, YJ [1 ]
Hwang, DH [1 ]
Sohn, DS [1 ]
机构：
[1] Korea Atom Energy Res Inst, Taejon 305600, South Korea
来源：
HEAT TRANSFER 1998, VOL 6: GENERAL PAPERS | 1998年
关键词：
D O I：
暂无
中图分类号：
O414.1 [热力学];
学科分类号：
摘要：
The effects of transverse mixing models between subchannels such as turbulent mixing and void drift have been investigated at single- and two-phase flow conditions. Three kinds of experimental data (PNL 2-channel, GE 9-rod, and ISPRA 16-rod experiments) have been evaluated by the subchannel analysis code COBRA-IV-I employing the simple void drift model of Lahey considering the tendency of void migration to wider channels. As the result of the analysis, a flow-pattern-dependent correction factor for the equilibrium void distribution term has been devised. It revealed that the proposed model successfully predicts the lower-than-average qualities of corner subchannels.
引用
收藏
页码：33 / 38
页数：6
相关论文
共 50 条
  • [21] Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRA
    Hwang, Dae-Hyun
    Kim, Seong-Jin
    Seo, Kyong-Won
    Kwon, Hyuk
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2012, 2012
  • [22] DEVELOPMENT AND PRELIMINARY VALIDATION OF THE FINE FUEL CELL SUBCHANNEL ANALYSIS CODE CUNLUN
    Jiang Hongwei
    Chen Guangliang
    Tian Zhaofei
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 6, ICONE31 2024, 2024,
  • [23] Development of a subchannel analysis code for SFR wire-wrapped fuel assemblies
    Sun, R. L.
    Zhang, D. L.
    Liang, Y.
    Wang, M. J.
    Tian, W. X.
    Qiu, S. Z.
    Su, G. H.
    PROGRESS IN NUCLEAR ENERGY, 2018, 104 : 327 - 341
  • [24] A subchannel analysis code MATRA-LMR for wire wrapped LMR subassembly
    Kim, WS
    Kim, YG
    Kim, YJ
    ANNALS OF NUCLEAR ENERGY, 2002, 29 (03) : 303 - 321
  • [25] THE PRINCIPLE AND PRELIMINARY VALIDATION OF A NEW SUBCHANNEL CODE
    Bai, Ning
    Zhu, Yuanbing
    Ren, Zhihao
    He, Haibo
    Lu, Haoliang
    Chen, Jun
    Li, Wenhuai
    Li, Jinggang
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 4, 2014,
  • [26] COMPREHENSIVE ASSESSMENT OF THE ISPRA BWR AND PWR SUBCHANNEL EXPERIMENTS AND CODE ANALYSIS WITH DIFFERENT 2-PHASE MODELS AND SOLUTION-SCHEMES
    WOLF, L
    FISCHER, K
    HERKENRATH, H
    HUFSCHMIDT, W
    NUCLEAR ENGINEERING AND DESIGN, 1987, 99 : 329 - 350
  • [27] Development of subchannel thermal-hydraulic analysis code for dual cooled annular fuel
    Saffari, A. H.
    Esmaili, H.
    PROGRESS IN NUCLEAR ENERGY, 2022, 150
  • [28] A subchannel analysis code SACOS-Na for sodium-cooled fast reactor
    Liang, Yu
    Zhang, Dalin
    Zhang, Jing
    Liu, Xiao
    Liu, Yapeng
    Zhou, Lei
    Chen, Yutong
    Wang, Xiaoyu
    Tian, Wenxi
    Qiu, Suizheng
    Su, Guanghui
    PROGRESS IN NUCLEAR ENERGY, 2023, 166
  • [29] Development of subchannel thermal-hydraulic analysis code for dual cooled annular fuel
    Saffari, A. H.
    Esmaili, H.
    PROGRESS IN NUCLEAR ENERGY, 2022, 150
  • [30] Coupled simulation for pin-wise reactor core analysis using subchannel analysis code CUPID and fuel performance code GIFT
    Lee, Yeong Hun
    Park, Jangkeun
    Choi, Youyeon
    Sim, Kyuseok
    Lee, Youho
    Cho, Hyoung Kyu
    ANNALS OF NUCLEAR ENERGY, 2025, 213
12345