Applicability of Empirical Correlations for Critical Heat Flux in Transfer Line Cool-Down Boiling

2021 ◽  
pp. 457-479
Author(s):  
Asit Kumar Meher ◽  
P. H. J. Venkatesh ◽  
M. S. R. Viswanath ◽  
J. Naga Raju ◽  
Ankit Kumar
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Empirical Correlations ◽  
Transfer Line

Pool Boiling Critical Heat Flux in Reduced Gravity

1999 ◽  
Vol 121 (4) ◽  
pp. 865-873 ◽  
Author(s):  
D. P. Shatto ◽  
G. P. Peterson
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Qualitative Data ◽  
Pool Boiling ◽  
Heat Fluxes ◽  
Reduced Gravity ◽  
Empirical Correlations ◽  
Using Data ◽  
Semi Empirical ◽  
Reduced Pressures

An experimental investigation has been conducted to measure pool boiling critical heat fluxes in reduced gravity. A horizontal cylindrical cartridge heater immersed in water at reduced pressures during parabolic flights on NASA’s KC-135 resulted in boiling on the heater surface. Visual observations and qualitative data trends indicate that the conventional Taylor-Helmholtz. instability model still governs the critical heat flux mechanism over the range of gravitational accelerations of the current study, which range from 0.0005 < g/go < 0.044. Using data from more than 40 individual tests, two semi-empirical correlations have been developed to account for the effect of thermocapillary flow, which tends to decrease the critical heat flux below the predictions of previous correlations.

A Brief Review of Computational Intelligence Techniques for Critical Heat Flux Prediction

2018 ◽  
Author(s):  
B. T. Jiang ◽  
Y. N. Liu
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Computational Intelligence ◽  
Nuclear Reactor ◽  
Nuclear Reactors ◽  
Nucleate Boiling ◽  
Operating Conditions ◽  
Maximum Efficiency ◽  
Support Vector ◽  
Empirical Correlations

Critical heat flux (CHF) is one of the important design criteria of water cooled nuclear reactors and plays a key role for the safety and economics of nuclear power plants (NPPs). One of the goals of nuclear reactor design is to receive maximum efficiency under full power and its efficiency would be improved when the core exit temperature increases. From this perspective, the design of a nuclear reactor needs to take into account the appropriate thermal margin to ensure that the fuel design limits are within acceptable limits for any normal operating conditions. However, in general, CHF limits the heat flux from the fuel rods and the power capacity of the nuclear reactor. CHF refers to the transition from nucleate boiling to film boiling and causes an abrupt rise of the fuel rod surface temperature. Therefore, prediction of CHF is vital to the design and safety analysis of water cooled nuclear reactors. During the last five decades, large efforts have been carried out on the CHF prediction by many researchers. Generally, CHF prediction can be achieved in three main ways: empirical correlations, look-up tables and phenomenological models. Due to the complex nature of CHF, there is no deterministic theory for the prediction of CHF. Even the look-up tables and the empirical correlations have their own application ranges and limitations. To overcome these limitations, some computational intelligence (CI) techniques have been developed for the prediction of CHF by many researchers in the last two decades. This paper provides a brief overview of CI techniques for prediction of CHF. In this paper, the reviewed CI techniques mainly include artificial neural networks (ANNs), genetic algorithms (GAs), support vector machines (SVMs), and their hybrid models. This review also compares the strengths and weaknesses of several CI techniques and provides basic technical support for future selection of appropriate methods by those involved in the field.

REVIEW OF CRITICAL HEAT FLUX IN A VERTICALLY DOWNWARD TWO PHASE FLOW

2018 ◽  
Author(s):  
Rajeshwar Sripada ◽  
Veeredhi Vasudeva Rao
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Two Phase Flow ◽  
Phase Flow ◽  
Two Phase

CRITICAL HEAT FLUX ENHANCEMENT ON NANOPILLAR ARRAY SURFACES

2018 ◽  
Author(s):  
Tuan Tran ◽  
Dongdong Liu ◽  
Binh-Thien Nguyen
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Flux Enhancement

INVESTIGATING THE RELATIONSHIP BETWEEN SURFACE WICKABILITY AND CRITICAL HEAT FLUX DURING POOL BOILING

2018 ◽  
Author(s):  
Youngsup Song ◽  
Yangying Zhu ◽  
Daniel J. Preston ◽  
H. Jeremy Cho ◽  
Zhengmao Lu ◽  
...  
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Pool Boiling ◽  
The Relationship
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