Advanced Liquid-Metal Thermal-Hydraulic Research for MYRRHA

Tichelen, Katrien Van; Kennedy, Graham; Mirelli, Fabio; Marino, Alessandro; Toti, A; Rozzia, Davide; Cascioli, Edoardo; Keijers, S.; Planquart, Philippe

doi:10.1080/00295450.2019.1614803

Cited by 21 publications

(6 citation statements)

References 27 publications

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“…Van Tichelen et al [ 94 ] conducted a thorough thermal-hydraulic analysis of occurrences in MYRRHA's engineering and safety assessments. They discovered that experimental programs support the validation of numerical tools and models in the well-established STH sector as well as in CFD.…”

Section: Analysis Of Thermal Hydraulics Activities Performed On Hlm-c...mentioning

confidence: 99%

Liquid metal cooled fast reactor thermal hydraulic research development: A review

Agbevanu

Arthur

Debrah

2023

Heliyon

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Section: Analysis Of Thermal Hydraulics Activities Performed On Hlm-c...mentioning

confidence: 99%

Liquid metal cooled fast reactor thermal hydraulic research development: A review

Agbevanu

Arthur

Debrah

2023

Heliyon

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“…In the framework of the MYRTE project, a new experimental facility was designed at the von Karman Institute for Fluid Dynamics (VKI) to carry out the experiments of (i) an unconfined BFS and (ii) a planar single jet (discussed in Section 2.4.1) (Van Tichelen et al, 2018;Buckingham, 2018). The MYRTE wind tunnel has the specificity of being a closed-loop sealed facility, thus enabling to test a transparent gas mixture composed of Helium and Xenon to reach the Prandtl number values lower than air.…”

Section: Forced Convection Unconfined Bfsmentioning

confidence: 99%

A collaborative effort towards the accurate prediction of turbulent flow and heat transfer in low-Prandtl number fluids

Shams

Roelofs

Tiselj

et al. 2020

Nuclear Engineering and Design

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“…It is one of the six most promising generation IV nuclear energy systems selected by the Generation IV Forum [1]. Many institutes have been committed to this field, and some research or experimental reactors are being or have been built [2], such as ALFRED [3], MYRRHA [4,5], SSTAR [6], and PASCAR [7].…”

Section: Introductionmentioning

confidence: 99%

PIV and CFD Study on Crossflow Characteristics in a 7-Pin Wire-Wrapped Bundle Channel

Fan

et al. 2023

International Journal of Energy Research

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China initiative Accelerator Driven System (CiADS) combines a linac, spallation target and a Lead-cooled Fast Reactor (LFR) together, which is designed to transmute nuclear waste and accelerate the progress of China’s energy technology research towards the goal of carbon neutrality. A LFR uses helical wire-wrap spacers as positioning components to enhance crossflow mixing in the reactor core. To study the velocity distribution and crossflow characteristics in wire-wrapped rod bundle channels, a 2 : 1 magnified scale 7-pin bundle fuel assembly model was fabricated using polymathic methacrylate. Particle image velocimetry (PIV) and computational fluid dynamics (CFD) simulations were used to investigate the velocity distribution in the 7-pin bundle flow channels at Reynolds number of 1250~5000 in the x z plane and Reynolds number of 1500 and 2500 in the x y plane. The deviation between CFD simulation results and PIV experimental data was small, and the Reynolds Average Navier-Stokes model could accurately simulate the flow characteristics of the wire-wrapped fuel rod bundle channels. The maximum crossflow velocity caused by helical wires was about 40% of the axial bulk velocity. The normalized crossflow velocity at the subchannel interface varied approximately sinusoidally with the axial height. As the Reynolds number increased, the velocity distribution trend and the loss rate of axial velocity in flow channels remained essentially constant while the peak value of crossflow velocity increased. The contour images of velocities with different axial heights were obtained from the x y plane, and their velocity distribution had a certain periodicity. The axial velocity loss rate in each subchannel caused by wire-wrap spacer resistance was between 7.35% and 38.51%, and the axial velocity loss rates in inner subchannels were usually higher than those in edge subchannels.

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Advanced Liquid-Metal Thermal-Hydraulic Research for MYRRHA

Cited by 21 publications

References 27 publications

Liquid metal cooled fast reactor thermal hydraulic research development: A review

Liquid metal cooled fast reactor thermal hydraulic research development: A review

A collaborative effort towards the accurate prediction of turbulent flow and heat transfer in low-Prandtl number fluids

PIV and CFD Study on Crossflow Characteristics in a 7-Pin Wire-Wrapped Bundle Channel

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