Modeling and validation of a mechanistic tool (MEFISTO) for the prediction of critical power in BWR fuel assemblies

Adamsson, Carl; Corre, Jean-Marie Le

doi:10.1016/j.nucengdes.2011.01.033

Cited by 28 publications

(3 citation statements)

References 17 publications

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“…Extracting the total mass flow rate and out of the derivative and re-expressing inside in actual quality parenthesis are indicated in equations (11), (12), and (13).…”

Section: Equations Governing the Flowmentioning

confidence: 99%

“…During the 90s, another approach MONA-3 is utilised [12]. Among other notable works; VIPRE-W [13], COBRA-TF [14], and most recently CATHARE-3 [15,16] -which was used in the NEPTUNE projectare introduced in the literature. However, as mentioned in the literature recently, none of these methods can come up with a robust solution for the complex nature of this [2].…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Theoretical Post-Dryout Heat Transfer Model

Tunç¹,

Esen²,

Sen³

et al. 2018

Int. J. Comput. Phys. Ser.

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A theoretical post-dryout heat transfer model is developed for two-phase dispersed flow, one-dimensional vertical pipe in a post-CHF regime. Because of the presence of average droplet diameter lower bound in a two-phase sparse flow. Droplet diameter is also calculated. Obtained results are compared with experimental values. Experimental data is used two-phase flow steam-water in VVER-1200, reactor coolant system, reactor operating pressure is 16.2 MPa. On heater rod surface, dryout was detected as a result of jumping increase of the heater rod surface temperature. Results obtained display lower droplet dimensions than the experimentally obtained values.

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“…Extracting the total mass flow rate and out of the derivative and re-expressing inside in actual quality parenthesis are indicated in equations (11), (12), and (13).…”

Section: Equations Governing the Flowmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Theoretical Post-Dryout Heat Transfer Model

Tunç¹,

Esen²,

Sen³

et al. 2018

Int. J. Comput. Phys. Ser.

View full text Add to dashboard Cite

show abstract

“…Another approach is to use the existing subchannel code as a driver tool which provides the subchannel conditions to the film dryout code. Adamsson et al [16] adopted similar approach using film flow code MEFISTO. The MEFISTO tool demonstrated that decoupling of the dryout analysis from the subchannel code is a feasible option and this approach promises to accommodate complex situation like part length fuel, unheated wall etc.…”

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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CFD model of diabatic annular two-phase flow using the Eulerian–Lagrangian approach

Anglart

2015

Annals of Nuclear Energy

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Modeling and validation of a mechanistic tool (MEFISTO) for the prediction of critical power in BWR fuel assemblies

Cited by 28 publications

References 17 publications

Theoretical Post-Dryout Heat Transfer Model

Theoretical Post-Dryout Heat Transfer Model

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

CFD model of diabatic annular two-phase flow using the Eulerian–Lagrangian approach

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