Experimental research on transient critical heat flux in vertical tube under oscillatory flow condition

Zhao, Dawei; Su, G.H.; Liang, Ziyu; Zhang, Y.J.; Tian, Wenxi; Qiu, Suizheng

doi:10.1016/j.ijmultiphaseflow.2011.06.012

Cited by 25 publications

(2 citation statements)

References 28 publications

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“…Some researchers conclude that the frequency of pulsations does not significantly affect heat transfer processes; others consider the flow pulsations as a deteriorating factor in heat transfer. Zhao et al [5] examine the heat transfer coefficient during boiling in a pulsating flow with a 1.04-10.6 s period. They discover that when boiling a two-phase flow, the local heat transfer coefficient is practically unaffected by a flow pulsation at the inlet.…”

Section: Introductionmentioning

confidence: 99%

The influence of microstructured surfaces and liquid pulsations on increasing heat transfer in a minichannel

Litvintceva,

Cheverda,

Agazhanov

2023

E3S Web Conf.

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The paper compares two methods for improving the intensification of heat transfer during boiling in a rectangular minichannel. Studies were carried out of the influence of additive structures on the crisis of heat transfer in a minichannel with a two-phase flow, as well as studies of the influence of high-frequency pulsations of liquid flow on the intensification of heat transfer processes during flow boiling.

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Section: Introductionmentioning

confidence: 99%

The influence of microstructured surfaces and liquid pulsations on increasing heat transfer in a minichannel

Litvintceva,

Cheverda,

Agazhanov

2023

E3S Web Conf.

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“…Li et al 16 developed the model, which predicts the CHF based on the back propagation (BP) neural network. Sensitivity coefficient of all the parameters was calculated by solving the differential equation of the BP model.…”

Section: Introductionmentioning

confidence: 99%

Experimental investigation of dryout phenomena under oscillatory flow conditions

et al. 2022

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In water-cooled nuclear reactors, the maximum power which can be extracted from the core is limited by critical heat flux (CHF). CHF in the high-quality region is known as dryout. In advanced nuclear reactors, the coolant flow occurs solely by virtue of natural circulation; however, instabilities may occur during off-normal operations. This may lead to premature dryout due to lower coolant flow rates seen by the heater during such oscillations. This paper describes the experimental investigation on the effect of flow oscillations on the CHF with the time period of 120 s, which is observed typically in the large-scale

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Current status of CHF predictions using CFD modeling technique and review of other techniques especially for non-uniform axial and circumferential heating profiles

Habib¹,

Nemitallah²,

El-Nakla³

2014

Annals of Nuclear Energy

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Experimental research on transient critical heat flux in vertical tube under oscillatory flow condition

Cited by 25 publications

References 28 publications

The influence of microstructured surfaces and liquid pulsations on increasing heat transfer in a minichannel

The influence of microstructured surfaces and liquid pulsations on increasing heat transfer in a minichannel

Experimental investigation of dryout phenomena under oscillatory flow conditions

Current status of CHF predictions using CFD modeling technique and review of other techniques especially for non-uniform axial and circumferential heating profiles

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