PTV/PIV measurements of turbulent flows in interior subchannels of a 61-pin wire-wrapped hexagonal fuel bundle

Goth, Nolan; Jones, P.; Nguyen, Thien; Vaghetto, Rodolfo; Hassan, Yassin A.; Salpeter, Nathaniel; Merzari, Elia

doi:10.1016/j.ijheatfluidflow.2018.03.021

Cited by 49 publications

(10 citation statements)

References 27 publications

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“…The velocity and pressure distribution within a 61-pins rod bundle is analyzed with the RANS model with wall functions. More precisely, the 61-pins matched-index-of-refraction experiment of Texas A&M University (Goth et al, 2018a, Goth et al, 2018b, Nguyen et al, 2017and Vaghetto et al, 2019 was selected for comparison. This experiment has been analyzed by Obabko et al (2016) by using wall resolved LES and by Mikuž (2019, 2020) by using wall resolved steady-state RANS, which is based on a linear and a nonlinear formulation of the SST k-ω model.…”

Section: Rans Analysis Of the Flow In A 61-pins Assemblymentioning

confidence: 99%

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Investigation of pressure loss and velocity distribution in fuel assemblies with wire-wrapped rods by using RANS and LES with wall functions

Bieder

Uitslag-Doolaard

Mikuž

2021

Annals of Nuclear Energy

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Section: Rans Analysis Of the Flow In A 61-pins Assemblymentioning

confidence: 99%

“…Comparison of the velocity distribution in selected measurement planes Goth et al (2018a and2018b) have published PIV measurements at Reynolds number Re ≈ 19300. As shown in Fig.…”

Section: 3mentioning

confidence: 99%

Investigation of pressure loss and velocity distribution in fuel assemblies with wire-wrapped rods by using RANS and LES with wall functions

Bieder

Uitslag-Doolaard

Mikuž

2021

Annals of Nuclear Energy

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“…Once the control testing is complete, the surface will be modified with carbon nanotube sheets to determine the effects of the surface on deposition (Kim, et al, 2018). The measurement techniques of PIV, PTV, and LIF (Estrada-Perez, et al, 2011;Goth, et al, 2018;Nguyen, et al, 2019) will be applied to the FPVS of VTR GFR Cartridge Loop in the future. The idea is to measure the deposition of surrogate particles within the facility.…”

Section: Summary and Future Workmentioning

confidence: 99%

Development of Innovative Measurement Techniques for Fission Product Transport Quantification

Orea

Choi

Nguyen

et al. 2020

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“…In the US, a validation program for wire wrapped rod bundles was established based on a 61-pin bundle. This comprised a MIR experiment (Goth et al, 2018a) and Nguyen et al (2017Nguyen et al ( , 2018, a heated experiment (Mays et al, 2016) and supplementary LES (Obabko et al, 2016). Through a US-EU collaboration, the LES data has been made available to EU partners in the frame of the SESAME project.…”

Section: -Pin Bundlementioning

confidence: 99%

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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PTV/PIV measurements of turbulent flows in interior subchannels of a 61-pin wire-wrapped hexagonal fuel bundle

Cited by 49 publications

References 27 publications

Investigation of pressure loss and velocity distribution in fuel assemblies with wire-wrapped rods by using RANS and LES with wall functions

Investigation of pressure loss and velocity distribution in fuel assemblies with wire-wrapped rods by using RANS and LES with wall functions

Development of Innovative Measurement Techniques for Fission Product Transport Quantification

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

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