Heat transfer experiment in a partially (internally) blocked 19-rod bundle with wire spacers cooled by LBE

Pacio, J.; Daubner, M.; Fellmoser, F.; Litfin, K.; Wetzel, Thomas

doi:10.1016/j.nucengdes.2018.01.034

Cited by 47 publications

(12 citation statements)

References 20 publications

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“…12 and two conditions, namely, small and large blockages, studied in Ref. 13. As shown in the figure, the predicted values are in good agreement with the experimental results for the four models.…”

Section: Model Comparison and Code Improvementsupporting

confidence: 79%

“…To study the thermal‐hydraulic behaviour of LBE flowing through the rod bundle, two experimental facilities, named Technologies for Heavy Metal Systems (THESYS) and Thermal‐Hydraulic and ADS Design (THEADES) were constructed by KALLA, 10 respectively. Based on THEADES facility, pressure drop and heat transfer characteristics for the 19‐rod bundle with grid and wire spacers were analysed, and different flow blockage conditions were considered 11‐13 . Additionally, KALLA studied the influence of IWF using three neighbouring hexagonal 7‐rod bundles with wire spacers in THESYS test loop 14 .…”

Section: Overview Of Previous Investigationsmentioning

confidence: 99%

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Improvement and validation of a sub‐channel analysis code for a lead‐cooled reactor with wire spacers

Wang

Gui

et al. 2020

Int J Energy Res

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Summary The fuel rods in the lead‐based fast reactor (LFR) are usually supported by wire spacer, and the presence of the wire results in the complexity of the thermal‐hydraulic analysis in rod bundles. In this study, several previous experimental research about lead‐bismuth eutectic flowing through the rod bundle are investigated. Based on the collected experimental data, a series of flow and heat transfer correlations in the wire‐fixed rod bundle are compared and evaluated. The recommended correlations are then implemented into the in‐house sub‐channel analysis code SACOS‐PB. Furthermore, to account for the changes in the channel cross‐section parameters caused by the wire spacer, two optional wire geometric treatments were added to the code: axially‐averaged approach and axially‐varied approach with extra cross‐flow enhancement model. 19‐rod bundle and 61‐rod bundle tests are used to validate the optimized code. The deviations for the temperature differences of cladding and coolant in internal sub‐channels are within 25%, and the axially‐varied approach shows a higher prediction accuracy, which proves that the improvement of the SACOS‐PB are reliable. This work could provide a reference for the subsequent design and development of the LFR core.

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Section: Model Comparison and Code Improvementsupporting

confidence: 79%

Section: Overview Of Previous Investigationsmentioning

confidence: 99%

Improvement and validation of a sub‐channel analysis code for a lead‐cooled reactor with wire spacers

Wang

Gui

et al. 2020

Int J Energy Res

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“…The total power of the fuel assembly, the inlet coolant temperature, and the mass flow rate are the same as that in the experiment. 13 Φ z…”

Section: Resultsmentioning

confidence: 99%

Thermal‐hydraulic analysis of wire‐wrapped rod bundle in lead‐based fast reactor with non‐uniform heat flux

Dong

Ahmad

Khan

et al. 2022

Intl J of Energy Research

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As one of the most promising advanced reactors, the lead-based fast reactor has drawn great attention due to economic and safety advantages. Investigating thermal hydraulics is essential for the design of a lead-based reactor.In this paper, a CFD simulation of a 19-wire-wrapped-rod bundle with leadbismuth eutectic (LBE) as coolant is carried out using the Reynoldsaveraged Navier-Stokes equation method, and four different types of axial non-uniform heat flux are applied. Excellent validation of results for thermal and hydraulic aspects is obtained first by comparing simulation results using turbulent model k-ω SST with experimental data and high-fidelity large eddy simulation data. The mechanism of transverse flow variation in subchannels and faces resulting from changing locations of wires is studied.

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“…Compared to the fuel assembly with grid-type spacers, wire-wrapped fuel assembly could generally achieve a lower pressure drop with a compact fuel rod packing (Todreas and Kazimi, 2011). Wire-wrapped fuel assembly are widely used in the Generation IV nuclear reactors, including the Sodium-cooled Fast Reactors (SFR) (Chen et al, 2018), the Lead-cooled Fast Reactors (LFR) (Pacio et al, 2018) and the Super Critical Water Cooled Reactors (SCWRs) (Shan et al, 2014). In the wire-wrapped fuel assembly, fuel rods are generally arranged in a hexagonal array, and the coolant flows in gaps around fuel rods, which are termed as the sub-channels.…”

Section: Introductionmentioning

confidence: 99%

Generating Hexahedral Mesh for Wire-wrapped Fuel Assembly With RBF Mesh Deformation Method

et al. 2021

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Fuel assemblies with wire spacer are widely used in Generation IV liquid nuclear reactors. With the rapid development of computational power, the Computational Fluid Dynamic (CFD) method is becoming an effective tool to investigate the detailed three-dimensional thermal hydraulic characteristics in wire-wrapped fuel assemblies. Due to the complexity of geometry, most of the published researches are performed with large number tetrahedron or polyhedral cells. The simulation is quite time-consuming and is generally limited to assemblies with small number of fuel pins. In this paper, a hexahedron meshing strategy is developed based on the Radial Basis Function (RBF) theory in present paper. This strategy would be beneficial for the modeling for the wire-wrapped fuel assemblies in real nuclear reactor core with large number of fuel pins. To validate this strategy, two experiments are simulated and detailed flow parameter distributions within the bundle, including the pressure distribution and the temperature distribution, have been compared. Good agreements have been achieved between the simulation results and the experimental results.

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Heat transfer experiment in a partially (internally) blocked 19-rod bundle with wire spacers cooled by LBE

Cited by 47 publications

References 20 publications

Improvement and validation of a sub‐channel analysis code for a lead‐cooled reactor with wire spacers

Improvement and validation of a sub‐channel analysis code for a lead‐cooled reactor with wire spacers

Thermal‐hydraulic analysis of wire‐wrapped rod bundle in lead‐based fast reactor with non‐uniform heat flux

Generating Hexahedral Mesh for Wire-wrapped Fuel Assembly With RBF Mesh Deformation Method

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