Experiment design to assess the inter-wrapper heat transfer in LMFR

Uitslag-Doolaard, Heleen; Roelofs, F.; Pacio, J.; Batta, A.

doi:10.1016/j.nucengdes.2018.11.019

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Analysis Of Thermal Hydraulics Activities Performed On Hlm-c...1

Analysis Of Engineering Example1

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Cited by 14 publications

(2 citation statements)

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“…Using RANS-based CFD simulation, a comparison between the novel bundle and the standard one was conducted to examine the new bundle heat transfer and fluid flow performance. Additionally, the impact of Inter-Wrapper Flow (IWF) on fuel assemblies with liquid metal cooling was investigated experimentally [ 62 , 63 ]. Furthermore, the CFD approach on a 19-pin wire-spaced fuel assembly using LBE was scaled to test the MYRRHA reactor’s fuel assembly [ 64 ].…”

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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“…Taking the design parameters of MYRRHA [23,24] lead-based reactor as an example, the coolant is liquid metal lead-bismuth eutectic(LBE), the fuel is stored in stainless steel cladding tubes, and the rod bundles are positioned radially by wire wrapping the cladding. Simple support constraints are adopted at both ends of the axial direction.…”

Section: Analysis Of Engineering Examplementioning

confidence: 99%

Dynamic Characteristics Analysis of Cylinders Bundle Coupling System Under Axial Flow

Shu

Yang

et al. 2021

mech

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Nuclear reactor fuel assemblies are mainly composed of cylinders bundle(CB), calculating the dynamics characteristics of CB under axial flow can lay a foundation for predicting fretting wear and vibration fatigue. In the paper, the CB coupling dynamic model of forced vibration under pulsating flow is established. And the stability analysis and natural frequency calculation of the CB system under steady flow are compared with the existing results to verify the model. Finally, the Runge-Kutta method is applied to solve the forced vibration equation of the CB under pulsating flow. The influence of the pulsating parameters m, w0, on the amplitude-frequency characteristics and the motion trajectory of the midspan cross section of the CB under forced vibration are analyzed and discussed. The results show that the pulsating parameters have an important influence on the vibration of the CB system.

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Experimental and numerical investigation on flow characteristics of inter-wrapper channel in LMFBR

Chen

Zhang

et al. 2021

Annals of Nuclear Energy

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Experiment design to assess the inter-wrapper heat transfer in LMFR

Cited by 14 publications

References 5 publications

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

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

Dynamic Characteristics Analysis of Cylinders Bundle Coupling System Under Axial Flow

Experimental and numerical investigation on flow characteristics of inter-wrapper channel in LMFBR

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