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Titlebook: Advances in Two-Phase Flow and Heat Transfer; Fundamentals and App S. Kaka?,M. Ishii Book 1983 Martinus Nijhoff Publishers, The Hague 1983

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樓主: choleric
31#
發(fā)表于 2025-3-26 21:11:48 | 只看該作者
Saleemul Huq,Jeffrey Chow,Helena Wrightties in single, double channel, cross-connected double channel, four parallel channel and four cross-connected parallel channel upflow systems are presented. The effects of heat flux variations, inlet subcoo1ing, flow rate, inlet and exit restrictions are indicated. The effect of heat transfer augme
32#
發(fā)表于 2025-3-27 01:41:38 | 只看該作者
33#
發(fā)表于 2025-3-27 06:24:52 | 只看該作者
34#
發(fā)表于 2025-3-27 11:25:25 | 只看該作者
Confronting Evil in International Relationsnresolved problems of two-phase fundamentals related to heat transfer equipment are summarized next based on the workshop discussion. The following individuals actively participated in the workshop session and/or provided written inputs: A. E. Bergles, J. G. Collier, F. Dobran, G. Farello, D. C. Gro
35#
發(fā)表于 2025-3-27 13:44:53 | 只看該作者
A Novel Approach for the Determination of Critical Two-Phase Flower to predict the critical flux of an evaporating fluid. These models are based on separated flow conditions in the fluid and use various criteria for the onset of critical flow. The present paper presents a method for the prediction of critical two-phase flow based on the positive entropy productio
36#
發(fā)表于 2025-3-27 21:35:19 | 只看該作者
37#
發(fā)表于 2025-3-27 21:58:08 | 只看該作者
38#
發(fā)表于 2025-3-28 04:56:15 | 只看該作者
Experimental Studies of Transient Flow Reversal in an Atmospheric Pressure Water Rigom up flow to downflow in the test section. The electrically heated test section power input was gradually increased in a series of experiments to produce a crisis in the apparatus. Results indicate that such a crisis would lead to eventual failure of the test section. Plots of the power and rate of
39#
發(fā)表于 2025-3-28 09:08:01 | 只看該作者
A Review of Two-Phase Flow Instabilitiesal years, demonstrating and explaining three different types of two-phase flow oscillations, namely, density-wave type, pressure-drop type oscillations and thermal oscillations, encountered in various boiling flow channel systems..Classification of two-phase flow instabilities is summarized first. T
40#
發(fā)表于 2025-3-28 11:34:24 | 只看該作者
The Modeling of Density-Wave Oscillations in Boiling Water Nuclear Reactorsumptions may lead to unnecessary operating restrictions. This paper presents a state-of-the-art-one-dimensional thermal-hydraulic model which can be used for the linear analysis of BWR stability. The model accounts for phasic slip, heated wall dynamics, distributed spacers, and a detailed model of t
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