Thermal Hydraulic Subchannel Model Based on Void-Drift

Rowe, D.S.; Macduff, Robert B.; Collingham, R.E.

doi:10.1615/ihtc9.4130

Cited by 5 publications

(2 citation statements)

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“…Form losses in the axial direction Carlucci [38], Rehme [39], Rao [40], Rosehart and Rogers [41] Inter-subchannel turbulent mixing and modified Carlucci inter-subchannel turbulent mixing Ohkawa and Lahey [42] Axial relative velocity, drift flux Wallis [43], Carlucci [38], Ohkawa and Lahey [42] Lateral relative velocity, lateral buoyancy drift velocity Carlucci [38], Rowe [44], Shoukri [45] Void diffusion coefficient Lahey and Moody [46], Rowe [44] Equilibrium void Pre-CHF heat transfer models Dittus-Boelter [47] Pre-CHF single-phase liquid heat transfer Chen [48] Pre-CHF 2-phase heat transfer Ahmad [49], Rouhani [50], Maróti [51], Lahey and Moody [46] Pre-CHF 2-phase heat transfer Hancox and Nicoll [52] Pre-CHF 2-phase heat transfer, interfacial heat transfer, H il Hammouda [53] Onset of nucleate boiling Ishii [54], Thurgood and Kelly [55], Maróti [51], Lahey and Moody [46] Interfacial heat transfer model: based on 4 simplified void fraction regions Thurgood and Kelly [55] Interfacial area: bubbly flow, bubbly-slug flow, churnturbulent flow, and annular flow Thurgood and Kelly [55], Maróti [51],…”

Section: Summary and Recommendationmentioning

confidence: 99%

Strategies for Developing Subchannel Capability in an Advanced System Thermalhydraulic Code: A Literature Review

Cheng

Rao

2015

AECL Nuclear Review

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In the framework of developing next generation safety analysis tools, Canadian Nuclear Laboratories (CNL) has planned to incorporate subchannel analysis capability into its advanced system thermalhydraulic code CATHENA 4. This paper provides a literature review and an assessment of current subchannel codes. It also evaluates three code-development methods: (i) static coupling of CATHENA 4 with the subchannel code ASSERT-PV, (ii) dynamic coupling of the two codes, and (iii) fully implicit implementation for a new, standalone CATHENA 4 version with subchannel capability. Results of the review and assessment suggest that the current ASSERT-PV modules can be used as the base for the fully implicit implementation of subchannel capability in CATHENA 4, and that this option may be the most cost-effective in the long run, resulting in savings in user application and maintenance costs. In addition, improved versatility of the tool could be accomplished by the addition of new features that could be added as part of its development. The new features would improve the capabilities of the existing subchannel code in handling low, reverse, and stagnant flows often encountered in system thermalhydraulic analysis. Therefore, the method of fully implicit implementation is preliminarily recommended for further exploration. A feasibility study will be performed in an attempt to extend the present work into a preliminary development plan.

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Section: Summary and Recommendationmentioning

confidence: 99%

Strategies for Developing Subchannel Capability in an Advanced System Thermalhydraulic Code: A Literature Review

Cheng

Rao

2015

AECL Nuclear Review

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“…In the similar way, a model for F I was selected by comparing dp/dz's obtained from Eqs. 7and (8). As a result, those correlations that were used in the following analysis are listed in Appendix.…”

Section: Total Pressure Gradientmentioning

confidence: 99%

Prediction of the Equilibrium Two-Phase Flow Distributions in Inter-Connected Subchannel Systems.

Shirai

Ninokata

2001

J. Nucl. Sci. Technol.

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This paper discusses the hydrodynamic equilibrium two-phase flow distribution phenomena in unheated subchannel systems. A set of two-fluid governing equations is solved and the solutions are compared with the equilibrium air-water two-phase flow experimental data from an interconnected two-subchannel test section in the slug to churn-turbulent flow regime. It is shown that the two-phase flow under the hydrodynamic equilibrium condition is distributed to make the minimum of possible pressure gradients. It is also shown that this minimum pressure gradient is closely related to the minimum energy dissipation of the total flow system. Finally a model is proposed to predict the hydrodynamic equilibrium two-phase flow distribution in a rod bundle as a minimization problem of the energy dissipation with mass continuity and momentum balance equations as the constraints.

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