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      KCI등재 SCIE SCOPUS

      A dryout mechanism model for rectangular narrow channels at high pressure conditions

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      https://www.riss.kr/link?id=A107075027

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      다국어 초록 (Multilingual Abstract)

      Adryoutmechanism model for rectangular narrow channels at high pressure conditions is developed byassuming that the KelvineHelmholtz instability triggered the occurrence ofdryout. This model combinesthe advantages of theoretical analysis and empirical...

      Adryoutmechanism model for rectangular narrow channels at high pressure conditions is developed byassuming that the KelvineHelmholtz instability triggered the occurrence ofdryout. This model combinesthe advantages of theoretical analysis and empirical correlation. The unknown coefficients in thetheoretical derivation are supported by the experimental data. Meanwhile, the decisive restriction of theexperimental conditions on the applicability of the empirical correlation is avoided. The expression ofvapor phase velocity at the time ofdryoutis derived, and the empirical correlation of liquidfilm thicknessis introduced. Since the CHF value obtained from the liquidfilm thickness should be the same as thevalue obtained from the KelvineHelmholtz critical stability under the same condition, the convergentCHF value is obtained by iteratively calculating. Comparing with the experimental data under thepressure of 6.89e13.79 MPa, the average error of the model is 15.4% with the 95% confidence interval[-20.5%, 10.4%]. And the pressure has a decisive influence on the prediction accuracy of this model.Compared with the existingdryoutcode, the calculation speed of this model is faster, and the calculationaccuracy is improved. This model, with great portability, could be applied to different objects andworking conditions by changing the expression of the vapor phase velocity when the dryout phenom-enon is triggered and the calculation formula of the liquidfilm.©2020 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under theCC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).1. IntroductionThe plate type fuel element has the advantages of compactstructure, high power per unit volume, low central temperature,high burnup, low heat storage and good safety. It is an advanceddesign structure of the new integrated pressurized water reactorcore. The coolantflow channel of the plate type fuel element is atypical rectangular narrow channel, which has compact structure,small temperature difference of heat transfer, simple surface pro-cessing, smoothness of heat transfer surface. Besides, it is not easyto produce impurities and pollute the heat transfer surface todeteriorate heat transfer with the high-speedfluid. Due to theabove characteristics, the rectangular narrow channel is widelyused in thefields of chemical, nuclear energy, electronic devicecooling, refrigeration and others. The research on the thermal hy-draulic properties of rectangular narrow channels has become a hotresearch topic [1,2].Critical heatflux (CHF) is the most important thermal hydrauliclimit parameter to ensure reactor core safety. When the criticalboiling occurs, theflow boiling mechanism of the coolant changes,the heat transfer coefficient decreases, and the heat transfer on thesurface of the nuclear fuel element deteriorates. In severe cases, thefuel element can be burned and even cause the radioactive leakage.It is generally believed that in region of the annularflow, CHF iscaused by liquidfilm drying, and the CHF model establishedaccordingly is called dryout model. Due to the wide range of quality(about 0.1e1.0) corresponding to the annularflow pattern, dryout isof great significance for the safety analysis and transient process ofboiling water reactors and pressurized water reactors. In recentyears, the dryout model has received much attention [3,4].In rectangular narrow channels, bubble growth is limited, and*Corresponding author.**Corresponding author.E-mail addresses:dlzhang@mail.xjtu.edu.cn(D. Zhang),dengjian_npic@163.com(J. Deng).Contents lists available atScienceDirectNuclear Engineering and Technologyjournal homepage:www.elsevier.com/locate/nethttps://doi.org/10.1016/j.net.2020.03.0181738-5733/©2020 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).Nuclear Engineering and Technology 52...

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      참고문헌 (Reference)

      1 T. Funada, "Viscous potential flow analysis of KelvineHelmholtz instability in a channel" 445 : 263-283, 2001

      2 D. X. Du, "Theoretical study on the characteristics of critical heat flux in vertical narrow rectangular channels" 36 : 21-31, 2012

      3 G. Su, "Theoretical calculation of annular upward flow in a narrow annuli with bilateral heating" 225 (225): 219-247, 2003

      4 G. B. Wallis, "The onset of slugging in horizontal stratified air-water flow" 1 (1): 173-193, 1973

      5 Y. Sudo, "Study on critical heat flux in rectangular channels heated from one or both sides at pressures ranging from 0. 1 to 14 MPa" 118 (118): 680-688, 1996

      6 D. Lu, "Study on CHF in thin rectangular channels and evaluation of its empirical correlations" 24 (24): 242-248, 2004

      7 G. Song, "RELAP5/MOD3. 4 calculation and model evaluation based on upper plenum entrainment experiment in AP1000" 138 : 107143-, 2020

      8 T. Okawa, "Prediction of the critical heat flux in annular regime in various vertical channels" 229 (229): 223-236, 2004

      9 T. Okawa, "Prediction of the critical heat flux in annular regime in various vertical channels" 229 (229): 223-236, 2004

      10 H. Utsuno, "Prediction of liquid film dryout in two-phase annularmist flow in a uniformly heated narrow tube development of analytical method under BWR conditions" 35 (35): 643-653, 1998

      1 T. Funada, "Viscous potential flow analysis of KelvineHelmholtz instability in a channel" 445 : 263-283, 2001

      2 D. X. Du, "Theoretical study on the characteristics of critical heat flux in vertical narrow rectangular channels" 36 : 21-31, 2012

      3 G. Su, "Theoretical calculation of annular upward flow in a narrow annuli with bilateral heating" 225 (225): 219-247, 2003

      4 G. B. Wallis, "The onset of slugging in horizontal stratified air-water flow" 1 (1): 173-193, 1973

      5 Y. Sudo, "Study on critical heat flux in rectangular channels heated from one or both sides at pressures ranging from 0. 1 to 14 MPa" 118 (118): 680-688, 1996

      6 D. Lu, "Study on CHF in thin rectangular channels and evaluation of its empirical correlations" 24 (24): 242-248, 2004

      7 G. Song, "RELAP5/MOD3. 4 calculation and model evaluation based on upper plenum entrainment experiment in AP1000" 138 : 107143-, 2020

      8 T. Okawa, "Prediction of the critical heat flux in annular regime in various vertical channels" 229 (229): 223-236, 2004

      9 T. Okawa, "Prediction of the critical heat flux in annular regime in various vertical channels" 229 (229): 223-236, 2004

      10 H. Utsuno, "Prediction of liquid film dryout in two-phase annularmist flow in a uniformly heated narrow tube development of analytical method under BWR conditions" 35 (35): 643-653, 1998

      11 J. Huang, "Numerical study on effect of gap width of narrow rectangular channel on critical heat flux enhancement" 239 (239): 320-326, 2009

      12 H.S. Jacket, "Investigation of Burnout Heat Flux in Rectangular Channels at 2000 Psia"

      13 K. Mishima, "Heat transfer study for thermalhydraulic design of the solid-target of spallation neutron source" 38 (38): 832-843, 2001

      14 W. Qu, "Flow boiling heat transfer in two-phase micro-channel heat sinkseeII. Annular two-phase flow model" 46 (46): 2773-2784, 2003

      15 L. Li, "Flow and heat transfer characteristics in platetype fuel channels after formation of blisters on fuel elements" 134 : 284-298, 2019

      16 F. Feind, "Falling liquid films with countercurrent air flow in vertical tubes" 481 : 5-35, 1960

      17 Y. W. Wu, "Experimental study on critical heat flux in bilaterally heated narrow annuli" 35 (35): 977-986, 2009

      18 R. Sun, "Experimental study of single-phase flow and heat transfer in rectangular channels under uniform and non-uniform heating" 110055-, 2020

      19 G. P. Celata, "Critical heat flux prediction for saturated flow boiling of water in vertical tubes" 44 (44): 4323-4331, 2001

      20 J. C. Sturgis, "Critical heat flux in a long, rectangular channel subjected to one-sided heatingdI. Flow visualization" 42 (42): 1835-1847, 1999

      21 Y. Sudo, "Critical heat flux at high velocity channel flow with high subcooling" 187 (187): 215-227, 1999

      22 F.E. Tippets, "Critical Heat Flux and Flow Pattern Characteristics of High Pressure Boiling Water in Forced Convection"

      23 Golgle Song, "Assessment of ECCMIX component in RELAP5 based on ECCS experiment" 한국원자력학회 52 (52): 59-68, 2020

      24 G. Su, "Application of an artificial neural network in reactor thermohydraulic problem : prediction of critical heat flux" 39 (39): 564-571, 2002

      25 F. A. N. Pu, "An investigation of flow characteristics and critical heat flux in vertical upward round tube" 17 (17): 170-176, 2006

      26 K. C. Tu, "A new mechanistic critical heat flux model at low-pressure and low-flow conditions" 124 (124): 243-254, 1998

      27 Y. Sudo, "A new CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors" 115 (115): 426-434, 1993

      28 Y. Sudo, "A CHF characteristic for downward flow in a narrow vertical rectangular channel heated from both sides" 15 (15): 755-766, 1989

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      2023 평가예정 해외DB학술지평가 신청대상 (해외등재 학술지 평가)
      2020-01-01 평가 등재학술지 유지 (해외등재 학술지 평가) KCI등재
      2014-01-01 평가 SCIE 등재 (등재유지) KCI등재
      2014-01-01 평가 SCOPUS 등재 (등재유지) KCI등재
      2011-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2009-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2007-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2006-07-31 학술지명변경 한글명 : Jorunal of the Korean Nuclear Society -> Nuclear Engineering and Technology
      외국어명 : 미등록 -> Nuclear Engineering and Technology
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      2004-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
      2003-01-01 평가 등재후보 1차 PASS (등재후보1차) KCI등재후보
      2002-01-01 평가 등재후보학술지 유지 (등재후보1차) KCI등재후보
      1999-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      2016 1.04 0.17 0.77
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.63 0.56 0.343 0.11
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