LOW QUALITY TRANSITION AND INVERTED ANNULAR-FLOW FILM BOILING OF WATER - AN UPDATED REVIEW

被引:13
作者
JOHANNSEN, K [1 ]
机构
[1] TECH UNIV BERLIN,INST ENERGIETECHN,W-1000 BERLIN 12,GERMANY
关键词
POST-CHF HEAT TRANSFER; TRANSITION BOILING; FILM BOILING; FLOW BOILING; REWETTING; LOCA;
D O I
10.1016/0894-1777(91)90030-U
中图分类号
O414.1 [热力学];
学科分类号
摘要
Post-critical heat flux heat transfer is of primary interest to safety analysis of certain postulated loss-of-coolant accidents of water-cooled nuclear reactors. Progress in the field has been reviewed periodically and assessed critically. This review covers experimental investigations of low quality transition and inverted annular flow film boiling of water in channels occurring after departure from nucleate boiling in temperature-controlled heat transfer systems. Rather than considering the return to nucleate boiling from the film boiling side, emphasis is given to the peculiarities of the steady-state boiling curve and corresponding prediction methods. A few of the special topics of critical review are the available experimental techniques for steady-state experiments, the limits of the transition boiling region, and the concept of surface contact in predicting transition boiling heat transfer. It is concluded that theoretical progress not considered in this review requires further experimental work.
引用
收藏
页码:497 / 509
页数:13
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  • [1] Groeneveld, Prediction Methods for Post-CHF Heat Transfer and Superheated Steam Cooling Suitable for Reactor Accident Analysis, Centre d'Etudes Nucleaire de Grenoble Report TT/SETRE/82-4-E/DGr, (1982)
  • [2] Groeneveld, Rousseau, CHF and Post-CHF Heat Transfer: An Assessment of Prediction Methods and Recommendations for Reactor Safety Codes, NATO Meeting on Advances in Two-Phase Flow and Heat Transfer, 1, pp. 203-239, (1983)
  • [3] Winterton, Transition Boiling, UKAEA Report AEEW-R 1567, (1982)
  • [4] Groeneveld, Inverted Annular and Low Quality Film Boiling: A State-of-the-Art Report, Presented at Int. Workshop on Fundamental Aspects of Post-Dryout Heat Transfer, (1984)
  • [5] Donevski, Chang, Groeneveld, Review of Interfacial Parameters Used in Inverted Annular Film Boiling, Presented at Fourth Miami Int. Symp. on Multi-Phase Transport and Particulate Phenomena, (1986)
  • [6] Bazho, Misak, Kantor, Evaluation of the Fuel Rod Cladding Temperature Calculation Conservatism due to Heat Transfer Selection Criteria, in Teplofizika 1982, Teplotekhnicheskaya Bezopasnost' Yadernykh Reactorov WWER, Vol. 2, Sbornic Dokladov iz Seminara SehV, pp. 170-178, (1982)
  • [7] Abel-Larsen, Olsen, Miettinen, Siikonen, Rasmussen, Et al., Heat Transfer Correlations in Nuclear Reactor Safety Calculations, Riso Natl. Lab. Rept. RISO-M-2504, 1-2, (1985)
  • [8] Misak, Bazso, Zeisler, A Study of the Sensitivity of PWR Core Thermal-Hydraulic Analysis for the Blowdown Phase of a Loss-of-Coolant Accident. Part I: Methods and Results of Analysis. Part II: Conclusions and Recommendations, Kernenergie, 28, pp. 113-118, (1985)
  • [9] Misak, Bazso, Zeisler, A Study of the Sensitivity of PWR Core Thermal-Hydraulic Analysis for the Blowdown Phase of a Loss-of-Coolant Accident. Part I: Methods and Results of Analysis. Part II: Conclusions and Recommendations, Kernenergie, 28, pp. 226-228, (1985)
  • [10] Analytis, Richner, Aksan, Assessment of Interfacial Shear and Wall Heat Transfer of RELAP5/MOD2/36.02 During Reflooding, EIR Rept. No. 624, (1987)