Heat transfer on HLM cooled wire-spaced fuel pin bundle simulator in the NACIE-UP facility

Piazza, Ivan Di; Angelucci, Morena; Marinari, R.; Tarantino, M.; Forgione, Nicola

doi:10.1016/j.nucengdes.2016.02.008

Cited by 61 publications

(14 citation statements)

References 10 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%

“…Also the geometry and operating conditions of the experiment in the NACIE facility described by Di Piazza et al (2016) are representative of the a fuel assembly envisaged for MYRRHA. For the NACIE experiments, the Reynolds number was varied from 1000 to 14 000 while the Péclet number varied from 25 to 250.…”

Section: Data Production Programmentioning

confidence: 99%

“…and more recently in is recommended. With respect to the NACIE experiments reported byDi Piazza et al (2016), the RANS simulations of NRG shown inFig. 6 (bottom)used a wall resolved mesh of about half the size of the mesh used to simulate…”

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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%

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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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“…The validation and calculations for benchmarks are widely implemented in different kinds of assemblies. The objects of experiments and simulations include a wire-wrapped annulus (Qin et al, 2019), 7- (Merzari et al, 2016), 19- (Pacio et al, 2016;Piazza et al, 2016;Pacio et al, 2017), 61- (Nguyen et al, 2017;Chen et al, 2018;Goth et al, 2018a;Goth et al, 2018b;Nguyen et al, 2018), and 127-pin assemblies (Kennedy et al, 2015), and for detailed outcomes, readers can refer to the paper by Roelof (Roelofs et al, 2019b) which makes key conclusions on these numeric practices. Among these studies, a variety of numerical results have confirmed the feasibility of the RANS models in simulating the turbulent heat transfer of liquid-metal coolants.…”

Section: Introductionmentioning

confidence: 99%

Numerical Study on the Thermal Hydraulic Characteristics in a Wire-Wrapped Assembly of LFRs

Fang

Guo

et al. 2020

Front. Energy Res.

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The concept of wire-wrapped assembly has been widely adopted in liquid metal-cooled reactors to enhance the capability of flow and heat transfer. The detailed 3D thermal hydraulic behaviors of liquid metal in the wire-wrapped assembly directly affect the safety of the reactor. In the present work, a numerical study on a 19-pin wire-wrapped assembly cooled by a lead-bismuth eutectic was carried out using the CFD method. The geometrical model is referred to in the test section in KIT’s 19-pin experiments, which is a scaled test assembly based on the MYRRHA reactor. The established CFD model was validated against experimental data and results showed that the SST k-ω model accompanied with the modified Prt was appropriate for the current problem. Then the numerical models were extensively used in the modeling of the blocked assembly flow with a cylindrical blockage. Also, the influences of blockage longitude, position, and porosity on the thermal hydraulic characteristics in the assembly were evaluated in detail. This work is meaningful for the deep understanding of safety features under the condition of assembly blockage operation in LFRs.

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“…Brasimone in Italy. The experience is related both to design and operation of such facilities and experimental results collected lead to publication in International research journals, see [4][5][6][7] as examples. At the ENEA C.R.…”

Section: Introductionmentioning

confidence: 99%

Conceptual Design of the CSP Lead Demonstrator SOLEAD

Piazza¹,

Tincani²,

Marinari³

et al. 2020

Adv. Mater. Lett.

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Heat transfer on HLM cooled wire-spaced fuel pin bundle simulator in the NACIE-UP facility

Cited by 61 publications

References 10 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

Numerical Study on the Thermal Hydraulic Characteristics in a Wire-Wrapped Assembly of LFRs

Conceptual Design of the CSP Lead Demonstrator SOLEAD

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