Phenomenological prediction of CHF under boiling water reactor (BWR) conditions

Chandraker, D. K.; Vijayan, P.K.; Sinha, R.K.; Aritomi, Masanori

doi:10.1016/j.pnucene.2011.02.013

Cited by 10 publications

(5 citation statements)

References 20 publications

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“…The applicable range of pressure is at 6.9 Mpa but Utsuno and Kaminaga [7] could successfully predict the dryout in a tube over the range from of 3 to 9 MPa, C/ρ g of 0.6 to 6.8 and the gas Reynolds number Re g of 1.6x10 5 to 6.6x10 5 . Also, Chandraker et al [8] predicted over the pressure range from 2.9-7.14 MPa for over 125 data points with a good accuracy.…”

Section: Constitutive Models For the Deposition Coefficient And Entramentioning

confidence: 92%

“…Over the years there have been significant improvements in the mechanistic prediction of dryout. Mechanistic prediction for a simple geometry has been found to be very good under BWR conditions as investigated by Utsuno et al [7] and Chandraker et al [8].…”

Section: Introductionmentioning

confidence: 93%

“…The code FIDOM-Rod (Film Dryout Modeling in Rod Bundle) is the extended version of the code, FIDOM [8] which was developed and validated for a dryout in a tube. The code, FIDOM-Rod uses the subchannel conditions determined by the subchannel code and initiates the film analysis as soon as the annular flow pattern prevails in the subchannels.…”

Section: Description Of the Models Of The Lfd Analysis (Fidom-rod)mentioning

confidence: 99%

“…It is found that Utsuno's model agrees well with the Okawa's model even beyond the range for high quality subchannels and Okawa tends to predicts lower for the low quality channels. In the present studies Utsuno's model has been used as it has been found to provide excellent dryout prediction for a tube under BWR condition [7,8].…”

Section: Comparison Of the Models For The Droplet Deposition Coefficimentioning

confidence: 99%

“…The constitutive models for the droplet entrainment and deposition rates play an important role for the good accuracy of the dryout prediction and hence the models tested for tube under the BWR operating conditions [7,8] has also been applied to the rod bundle in the present work using the subchannel conditions derived from the subchannel code COBRA-IV-I [17]. The lateral flow rate of the film on the rod is also an important aspect of the dryout modeling and the previous approaches mentioned above generally assume that the cross flow consists of vapor only and liquid contribution is negligible [15].…”

Section: Introductionmentioning

confidence: 99%

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A Mechanistic Approach for the Prediction of Critical Power in BWR Fuel Bundles

Chandraker

Vijayan

Sinha

et al. 2012

JPES

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The critical power corresponding to the Critical Heat Flux (CHF) or dryout condition is an important design parameter for the evaluation of safety margins in a nuclear fuel bundle. The empirical approaches for the prediction of CHF in a rod bundle are highly geometric specific and proprietary in nature. The critical power experiments are very expensive and technically challenging owing to the stringent simulation requirements for the rod bundle tests involving radial and axial power profiles. In view of this, the mechanistic approach has gained momentum in the thermal hydraulic community. The Liquid Film Dryout (LFD) in an annular flow is the mechanism of CHF under BWR conditions and the dryout modeling has been found to predict the CHF quite accurately for a tubular geometry. The successful extension of the mechanistic model of dryout to the rod bundle application is vital for the evaluation of critical power in the rod bundle. The present work proposes the uniform film flow approach around the rod by analyzing individual film of the subchannel bounded by rods with different heat fluxes resulting in different film flow rates around a rod and subsequently distributing the varying film flow rates of a rod to arrive at the uniform film flow rate as it has been found that the liquid film has a strong tendency to be uniform around the rod. The FIDOM-Rod code developed for the dryout prediction in BWR assemblies provides detailed solution of the multiple liquid films in a subchannel. The approach of uniform film flow rate around the rod simplifies the liquid film cross flow modeling and was found to provide dryout prediction with a good accuracy when compared with the experimental data of 16, 19 and 37 rod bundles under BWR conditions. The critical power has been predicted for a newly designed 54 rod bundle of the Advanced Heavy Water Reactor (AHWR). The selected constitutive models for the droplet entrainment and deposition rates validated for the dryout in tube were also found to perform well for the rod bundle under BWR conditions.

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Section: Constitutive Models For the Deposition Coefficient And Entramentioning

confidence: 92%

Section: Introductionmentioning

confidence: 93%

Section: Description Of the Models Of The Lfd Analysis (Fidom-rod)mentioning

confidence: 99%

Section: Comparison Of the Models For The Droplet Deposition Coefficimentioning

confidence: 99%