A numerical analysis for a damage propagation in a plate-type fuel assembly of a research reactor

Park, Jong Pil; Park, Cheol; Park, Su-Ki

doi:10.1016/j.anucene.2020.108071

Cited by 3 publications

(2 citation statements)

References 21 publications

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“…Under high-performance design requirements, the narrow rectangular-fuel assembly was adopted in UFR with higher heat exchange capacity (Park et al, 2021). Unlike the coolant channel form of rod bundle fuel assemblies, the coolant channel is narrow rectangular with a channel gap of only 2-3 mm.…”

Section: Introductionmentioning

confidence: 99%

Study on flow and heat transfer characteristics of liquid metal flow in narrow rectangular channels under high heat flux

Zhang,

Feng,

et al. 2024

Front. Energy Res.

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In order to improve the core power density of liquid metal reactors, narrow rectangular fuel assemblies are typically used, which have obvious advantages in heat transfer capacity. However, the flow and heat transfer characteristics in coolant passage need to be studied. In this article, the numerical simulation analysis model obtained earlier was applied to calculate the Nusselt number, friction factor, with different Reynolds number, Prandtl number, or Peclet number of lead bismuth flow in a narrow rectangular channel under high heat flux. A heating correction factor was proposed and a flow resistance model was established for high heat flux. The influencing factors of ultra-high flux reactor core, such as gap size, flow direction, single and double sided heating conditions, on the flow and heat transfer in narrow rectangular channels were explored. The results showed that gap size and aspect ratio have a certain impact on the Nu and f of narrow rectangular channels, but the influence is relatively small within the narrow rectangular channel condition range. The influence of flow direction on flow and heat transfer is minimal, the single and double sided heating conditions will bring about a difference of about 20% in Nu and a difference of about 2.5% in f. In addition, the type of liquid metal will also affect the results. The research can provide reference for the thermal design and optimization of ultra-high flux reactor cores.

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Section: Introductionmentioning

confidence: 99%

Study on flow and heat transfer characteristics of liquid metal flow in narrow rectangular channels under high heat flux

Zhang,

Feng,

et al. 2024

Front. Energy Res.

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“…Guo et al (2018) found when the blockage ratio of the fuel assembly is 70%, the departure from nucleate boiling will occur. Park et al (2021) investigated the thermalhydraulic behaviors of flow channels of the plate-type fuel assembly by the CFD simulation with a multi-phase flow model. The wall boiling model proposed by Kurul and Podowski (1991) was used and the influence of the flow channel blockage on the flow instability and heat transfer was studied.…”

Section: Introductionmentioning

confidence: 99%

Numerical Investigation of Conjugated Heat Transfer of the Plate-Type Fuel Assembly in the Research Reactor

Quan

et al. 2021

Front. Energy Res.

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In nuclear reactors, the research of conjugated heat transfer between the fuel and coolant in the fuel assembly is fundamental for improving the safety, reliability and economy. The numerical approach based on Computational Fluid Dynamics (CFD) can be used to realize the rapid analysis of the conjugated heat transfer. Besides, the numerical simulation can provide detailed physical fields that are useful for the designing and optimizing of the fuel assembly. The plate-type fuels are generally used to enhance heat transfer in research reactors with high power density. In this study, a standard plate-type fuel assembly in the research reactor was taken into consideration. The solid-fluid conjugated heat transfer of the fuel assembly and coolant was numerically investigated. In the fluid region, the subcooled flow boiling simulation model was established by implementing the Rensselaer Polytechnic Institute model into the Euler multi-phase flow method. The results show that the conjugated heat transfer of the fuel assembly and coolant can be simulated using the model established in this work. The influence of fluid velocity, power density and the width of the flow channel on the temperature distribution and the conjugated heat transfer was investigated and discussed.

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Neutronic calculations and thermalhydraulic application using CFD for the nuclear research reactor NUR at steady state mode

Sidi-Ali

Medouri

Ailem

et al. 2023

Progress in Nuclear Energy

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A numerical analysis for a damage propagation in a plate-type fuel assembly of a research reactor

Cited by 3 publications

References 21 publications

Study on flow and heat transfer characteristics of liquid metal flow in narrow rectangular channels under high heat flux

Study on flow and heat transfer characteristics of liquid metal flow in narrow rectangular channels under high heat flux

Numerical Investigation of Conjugated Heat Transfer of the Plate-Type Fuel Assembly in the Research Reactor

Neutronic calculations and thermalhydraulic application using CFD for the nuclear research reactor NUR at steady state mode

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