Experimental investigation on repeatability of CHF in rod bundle with non-uniform axial heat flux distribution-Reference-Cited by-同舟云学术

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Experimental investigation on repeatability of CHF in rod bundle with non-uniform axial heat flux distribution

Published:2016-07 Issue: Volume:90 Page:151-154
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Qin Shengjie,Lang Xuemei,Xie Shijie,Li Pengzhou,Zhuo Wenbin,Liu Wenxing,Zhang Junyi

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference10 articles.

1. Prediction of CHF in concentric-tube open thermosiphon using artificial neural network and genetic algorithm;Chen;Heat. Mass Transf.,2010

2. Analysis of CHF in saturated forced convective boiling on a heated surface with impinging jets using artificial neural network and genetic algorithm;Cong;Nucl. Eng. Des.,2011

3. Benchmark testing the ODEN CHF loop to Columbia university HTRF;David Smith,2011

4. Analysis of the critical heat flux in round vertical tubes underlow pressure and flow oscillation conditions. Applications of artificial neural network;Guanghui;Nucl. Eng. Des.,2003

5. Comparison of PWR fuel assembly CHF tests obtained at three different test facilities;Herer,2005

Cited by 11 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. The influence of turbulators on the flow and heat transfer characteristic of helium-xenon mixture inside the tight lattice rod bundles;International Journal of Heat and Fluid Flow;2024-09

2. An experimental research of the influence on critical heat flux of a rod bundle under certain inlet temperatures;Frontiers in Energy Research;2024-07-29

3. An Experimental Study of the Critical Heat Flux in a Square Channel with Non-Uniformly Heated Rod Under Low Pressure and Low Flow Conditions;2024

4. A review on dryout and Post-dryout heat transfer inside tubes and tube bundles;Applied Thermal Engineering;2023-01

5. Experimental investigation on onset of nucleate boiling and flow boiling heat transfer in a 5 × 5 rod bundle;Applied Thermal Engineering;2022-05

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