A Phenomenological Model for Prediction of Critical Heat Flux under Highly Subcooled Conditions

Weisman, J.; Ileslamlou, Shahab

doi:10.13182/fst88-a25140

Cited by 97 publications

(8 citation statements)

References 5 publications

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“…The critical void fraction a b is empirically set at 0.82, which corresponds to oval bubbles with long to short radius ratio of 3 to 1 are packed in the bubbly layer. To adapt the model better to high subcooling region, Weisman and Ileslamlou [6] extended the Weisman-Pei model by using basic energy balance for the bubbly layer to compute the CHF. The approaches of Weisman and coworkers show good accuracy to high-pressure water data, liquid nitrogen data and Feron 113 data.…”

Section: Bubble Crowding Modelmentioning

confidence: 99%

Viewpoint of Subcooled Flow Boiling Critical Heat Flux Mechanism

Liu

Nariai²

2002

Chem. Eng. Technol.

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Section: Bubble Crowding Modelmentioning

confidence: 99%

Viewpoint of Subcooled Flow Boiling Critical Heat Flux Mechanism

Liu

Nariai²

2002

Chem. Eng. Technol.

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“…In addition, they revised the calculation for bubble diameters and included the slip ratio in the bubble layer to improve CHF prediction at low mass flow rates. Weisman and Illeslamlou (1988), on the other hand, extended the model to high subcooling conditions based on the energy balance at the outer edge of the bubble layer in round tubes. Chang and Lee (1989) revised the calculation of the lateral mass velocity from the core to the bubble layer at low qualities in uniformly heated tubes in their CHF model.…”

Section: Introductionmentioning

confidence: 99%

Assessment of a Theoretical Model for Predicting Forced Convective Critical Heat Flux in Rod Bundles

Yang

Yin²,

Shan

et al. 2019

Front. Energy Res.

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This study proposes a theoretical model for predicting forced convective critical heat flux (CHF) in rod bundles based on the bubble crowding phenomenon. The theoretical model applied to the rod bundle is based on Weisman-Pei's basic tube model. In order to make it suitable for rod bundles in Pressurized Water Reactors (PWR), the flow and heat transfer characteristics of rod bundles are considered, including velocity distribution, flow patterns, the grid effect on CHF, and turbulence intensity. The theoretical model is applied together with the subchannel code ATHAS to assess it against uniformly heated CHF data obtained from a 5 × 5 rod bundle, and good agreement is observed.

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“…boundary layer separation model (Tong, 1968), bubble crowding model (Joel Weisman, 1988), interfacial lift-off model (Galloway and Mudawar, 1993b), sublayer dryout model (Lee and Mudawwar, 1988), have been postulated as the trigger for CHF in subcooled and near-saturated flow boiling. All these mechanisms were based upon some physical process that blocks fresh liquid flow from reaching the heated wall.…”

Section: Introductionmentioning

confidence: 99%