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

Abstract

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.

SESAME project: advancements in liquid metal thermal hydraulics experiments and simulations

“…Moroever, quasi-DNS simulation data was generated for a rod bundle with an infinite number of pins and LES data was generated for a 61-pin bundle. In [25], the work on validating RANS CFD methods for wire-wrapped fuel assemblies is summarized. It is concluded that validation efforts up to now indicate that an accuracy within 12.5% for engineering RANS models should be feasible for all bundle sizes and all parameters checked.…”

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

“…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.…”