Critical Power Analysis with Mechanistic Models for Nuclear Fuel Bundles, (I)

Naitoh, Masanori; Ikeda, Takashi; Nishida, Koji; Okawa, Tomio; Kataoka, Isao

doi:10.1080/18811248.2002.9715155

Cited by 20 publications

(2 citation statements)

References 17 publications

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“…Recently, a number of three-fluid models were developed to predict the thermal-hydraulic parameters in annular flow. [22][23][24] Compared to the mixture model, three-fluid models have more sophisticated characteristics and potential to be further developed. They are fitted to the simulation of transients and non-equilibrium conditions.…”

Section: One-dimensional Mixture Modelmentioning

confidence: 99%

Numerical Simulation of Liquid Drop Deposition in Annular-Mist Flow Regime of Boiling Water Reactor

Xie

Koshizuka

Oka

2004

Journal of Nuclear Science and Technology

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The deposition process of a single droplet on the liquid film is numerically simulated by the Moving Particle Semi-implicit (MPS) method to analyze the possibility and effect of splash occurring in Boiling Water Reactor (BWR) condition. A simple one-dimensional mixture model is used to calculate the necessary parameters for the simulation of deposition. The rationality of the model is confirmed by comparison with the experimental results. A film buffer model is developed to arrange the simulation results. A correlation of the critical impact Weber number for splash is obtained. It is found that splash and subsequent re-entrainment process is significant and cannot be ignored in the high quality condition in BWR.

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Section: One-dimensional Mixture Modelmentioning

confidence: 99%

Numerical Simulation of Liquid Drop Deposition in Annular-Mist Flow Regime of Boiling Water Reactor

Xie

Koshizuka

Oka

2004

Journal of Nuclear Science and Technology

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“…Codes like SILFEED [9.10,11], FIDAS [12], CAPE-BWR [13], COBRA/BWR [14] etc. have been developed and compared with the experimental data achieving good accuracy.…”

Section: Introductionmentioning

confidence: 99%

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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