Turbulent mixing in a rod bundle with vaned spacer grids: OECD/NEA–KAERI CFD benchmark exercise test

Chang, Si Young; Kim, Seok; Song, Chul-Hwa

doi:10.1016/j.nucengdes.2014.05.013

Cited by 75 publications

(8 citation statements)

References 11 publications

(11 reference statements)

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“…Following the examples of Chang et al [11], a swirling factor (F swirl ) and a mixing factor (F mix ) are defined to quantify the swirling and inter-subchannel crossflow, respectively. The absolute value of normalized velocity is averaged over the diagonal lines to obtain the swirling factor and over the gap lines to obtain the mixing factor (Figure 6).…”

Section: Momentum Source Model Setupmentioning

confidence: 99%

Initial full core SMR simulations with NekRS

Merzari

Fang

Shaver

et al. 2020

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Section: Momentum Source Model Setupmentioning

confidence: 99%

Initial full core SMR simulations with NekRS

Merzari

Fang

Shaver

et al. 2020

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“…In the past years, researches have been carried out to study these phenomena of turbulence and pressure drop caused by spacer grids in order to achieve an optimized system [2,3,4]. The turbulence has been measured mainly by Laser Doppler Velocimetry (LDV) and Particle Image Velocimetry (PIV) [5,6]. With these techniques is possible to see some specifics patterns in the flow e.g.…”

Section: Introductionmentioning

confidence: 99%

Numerical and experimental investigation of the water flow through PWR spacer grids

et al. 2021

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Spacer grids are one of main components of a Pressurized Water Reactor (PWR) fuel assembly. They are able to improve heat transfer from rod bundles to the water flow by increasing turbulence and mixture of this flow. On the other hand the pressure drop increases because spacer grids. Experimental and Computational Fluid Dynamics (CFD) analysis have been used to understand how spacer grids affect the water flow. This analysis is important to improve spacer grids thermal-hydraulic performance. This paper aims to investigate numerically and experimentally the water flow through PWR spacer grids. The numerical and experimental procedures have been developed for a 5x5 rod bundle with spacer grids at the Nuclear Technology Development Center (CDTN) in Belo Horizonte, Brazil. At CDTN, measurements of the velocity components are acquired with a 2D LDV (Laser Doppler Velocimetry) system and the numerical results are obtained using ANSYS CFX code. The measurements are obtained at one height downstream from a spacer grid and compared to CFD simulations for a flow rate at Reynolds number of 5.4x104 . Results show good agreement between both methodologies. The great repeatability and low experimental uncertainty evaluated (< 1.24%) in this work can be used to validate other CFD codes.

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“…Chang et al, [1] and Xiong et al, [2] utilized a LDV-2D and 3D, respectively, for axial and lateral velocities profiles evaluation of the water flow through a test rig with a mixing vane spacer grids.…”

Section: Introductionmentioning

confidence: 99%

5X5 Rod Bundle Flow Field Measurements Downstream a PWR Spacer Grid

Castro

Silva²,

Santos³

et al. 2020

Braz. J. Rad. Sci.

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The spacer grids are structures present in nuclear fuel assembly of Pressurized Water Reactors (PWR). They play an important structural role and also assist in heat removal through the assembly by promoting increased turbulence of the flow. Understanding the flow dynamics downstream the spacer grid is paramount for fuel element design and analysis. This paper presents water flow velocity profiles measurements downstream a spacer grid in a 5x5 rod bundle test rig with the objective of highlighting important fluid dynamic behavior near the grid and supplying data for CFD simulation validation. These velocity profiles were obtained at two different heights downstream the spacer grid using a LDV (Laser Doppler Velocimetry) through the top of test rig. The turbulence intensities and patterns of the swirl and cross flow were evaluated. The tests were conducted for Reynolds numbers ranging from 1.8x104 to 5.4x104. This experimental research was carried out in thermohydraulics laboratory of Nuclear Technology Development Center – CDTN. Results show great repeatability and low uncertainties (< 1.24 %). Details of the flow field show how the mixture and turbulence induced by the spacer grid quickly decays downstream the spacer grid. It is shown that the developed methodology can supply high resolution low uncertainty results that can be used for validation of CFD simulations.

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Turbulent mixing in a rod bundle with vaned spacer grids: OECD/NEA–KAERI CFD benchmark exercise test

Cited by 75 publications

References 11 publications

Initial full core SMR simulations with NekRS

Initial full core SMR simulations with NekRS

Numerical and experimental investigation of the water flow through PWR spacer grids

5X5 Rod Bundle Flow Field Measurements Downstream a PWR Spacer Grid

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