Experimental study of heavy-liquid metal (LBE) flow and heat transfer along a hexagonal 19-rod bundle with wire spacers

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

doi:10.1016/j.nucengdes.2016.03.003

Cited by 99 publications

(19 citation statements)

References 20 publications

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“…In Europe, two independent sets of experiments on 19-pin heated bundles in liquid metal were performed by Di Piazza et al (2016) and Pacio et al (2016). The first one focused on natural convection conditions, while the second one focused on forced convection conditions.…”

Section: -Pin Bundlementioning

confidence: 99%

“…The geometry and operating conditions of temperature, flow velocity and power density of the experiment in the KALLA facility described by Pacio et al (2016) are representative for the fuel assemblies envisaged for the lead-bismuth cooled MYRRHA reactor under design in Belgium. For this experiment, an extensive test matrix comprising of more than 30 experimental runs was analysed.…”

Section: Data Production Programmentioning

confidence: 99%

“…The 19-pin heated experiments in the KALLA facility reported by Pacio et al (2016) were used to validate RANS modelling. This effort is described in Pacio et al (2017).…”

Section: Numerical Programmentioning

confidence: 99%

“…Fig. 6 (top) shows an example of temperature predictions for the experiments of Pacio et al (2016) leading to the conclusion that heat transfer (Nusselt number) can be predicted within 12% (Pacio et al, 2017) using a wall resolved mesh and an SST k-ω model with a default constant turbulent Prandtl number of 0.9. A future assessment of the impact of using more advanced turbulent heat flux models as described in Roelofs et al (2015) the experiments in the KALLA facility, i.e.…”

Section: Numerical Programmentioning

confidence: 99%

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Towards validated prediction with RANS CFD of flow and heat transport in a wire-wrap fuel assembly

Roelofs

Uitslag-Doolaard

Dovizio

et al. 2019

Nuclear Engineering and Design

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Liquid metal fast reactors (LMFRs) are foreseen to play an important role in the future of nuclear energy, thanks to their increased fuel utilization and safety features profiting from the optimal heat transfer performance of the metallic coolants. Accurate thermal-hydraulic analysis of their fuel assemblies, typically employed with wire-wraps as spacers, is recognized as a crucial scientific and engineering contribution to support the deployment of such technology. This challenges the modeling and simulation community. To this aspect, various reference databases (both experimental and numerical) for different wire-wrapped fuel assembly configurations have been created recently and are being used for validation of engineering simulation approaches based on Reynolds Averaged Navier Stokes (RANS) modelling. These databases include: • 7-pin rod bundle: A detailed experiment with Particle Image Velocimetry (PIV) is performed. In order to allow accurate measurements of the flow topology, a matched-index-of-refraction technique was used employing water as working fluid. • 19-pin bundle: A series of experiments is performed covering a wide range of Reynolds and Peclet numbers as well as thermal powers. The experiments use liquid lead-bismuth eutectic as working fluid. The measurements include pressure drop and local temperatures. • 61-pin rod bundle: This large eddy simulation including conjugate heat transfer from the pin cladding to the coolant allows to bridge the gap from small bundles (less than 37 pins) to large bundles (more than 37 pins). In literature, a fundamental different behavior has been observed for small bundles compared to large bundles. • 127-pin bundle: Isothermal experiments using lead-bismuth eutectic characterizing pressure drop are performed on a full scale fuel assembly representative for the MYRRHA reactor. • Infinite pin bundle: This reference quasi-direct numerical simulation profits from periodicity in all directions. It provides a detailed view into the flow field and in addition reveals details of the heat transfer from the rod bundle into the flow. Reference databases aim to serve the nuclear scientific community to validate engineering simulation approaches. The paper will introduce these reference databases, and how they have been used to validate RANS based turbulence modelling approaches within a mainly European context.

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Section: -Pin Bundlementioning

confidence: 99%

Section: Data Production Programmentioning

confidence: 99%

“…The 19-pin heated experiments in the KALLA facility reported by Pacio et al (2016) were used to validate RANS modelling. This effort is described in Pacio et al (2017).…”

Section: Numerical Programmentioning

confidence: 99%

Section: Numerical Programmentioning

confidence: 99%

See 2 more Smart Citations

Towards validated prediction with RANS CFD of flow and heat transport in a wire-wrap fuel assembly

Roelofs

Uitslag-Doolaard

Dovizio

et al. 2019

Nuclear Engineering and Design

Self Cite

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“…A prominent example for such an integral scaled experiment is provided by the KALLA (Karlsruhe Liquid Metal Laboratory) fuel bundle experiment, shown in Figure and described in detail in Refs. .…”

Section: Liquid Metals In Scientific and Nuclear Research Installationsmentioning

confidence: 99%

Liquid Metals as Efficient High‐Temperature Heat‐Transport Fluids

et al. 2017

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Liquid metals appear to be attractive heat‐transport fluids, in particular if looking at their high thermal conductivities and low viscosities. Despite some pioneering technical applications in the past, complex handling, special requirements, safety concerns, and structural degradation of the materials have prevented their widespread application. However, progress in research and development on liquid‐metal science and technology has advanced considerably in the last decade, and this has opened the gate to their broader use in the short term. This requires a more differentiated view on liquid metals, particularly on the specific properties of individual fluids within the context of specific applications. By doing so, many commonly mentioned prejudices vanish or are of minor significance. At the Karlsruhe Institute of Technology, a comprehensive research program on liquid‐metal technology has been pursued for more than 50 years, and some of the advances in different applications will be outlined in this article.

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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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Experimental study of heavy-liquid metal (LBE) flow and heat transfer along a hexagonal 19-rod bundle with wire spacers

Cited by 99 publications

References 20 publications

Towards validated prediction with RANS CFD of flow and heat transport in a wire-wrap fuel assembly

Towards validated prediction with RANS CFD of flow and heat transport in a wire-wrap fuel assembly

Liquid Metals as Efficient High‐Temperature Heat‐Transport Fluids

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

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