Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed core

Liu, Limin; Zhang, Dalin; Li, Linfeng; Yang, Yicheng; Wang, Chenglong; Qiu, Suizheng; Su, G.H.

doi:10.1016/j.applthermaleng.2018.09.017

Cited by 32 publications

(19 citation statements)

References 24 publications

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“…Based on the above pressure drop variation method, Liu et al 3 determined the range of the transition and turbulent flow regimes for the high‐Prandtl‐number fluid in the pebble‐bed nuclear reactor core of FHRs.…”

Section: Flow Characteristics In the Pebble Bedmentioning

confidence: 99%

“…One factor that contributed to the difference was the different choice of fluid velocity and characteristic length. Definitions of the Reynolds number are as follows 3,24‐27,31 :

\begin{matrix} centertrue \\ Re = \frac{ρ {italicud}_{p}}{μ}; {italicRe}_{p 1} = \frac{ρ {italicud}_{p}}{μ}; {italicRe}_{p 2} = \frac{ρ u_{p} d_{p}}{μ} \\ {italicRe}_{dh 1} = \frac{ρ {italicud}_{h 1}}{μ}; {italicRe}_{dh 2} = \frac{ρ u_{p} d_{h 2}}{μ}; {italicRe}_{dh 3} = \frac{ρ u_{p} d_{h 1}}{μ} \end{matrix}

where d p is the pebble diameter; u , the superficial velocity;

d_{p}^{'}

, the pore diameter and u p , the pore velocity. d h 1 and d h 2 are the pebble bed hydraulic diameters, which are defined as follows:

d_{h 1} = \frac{2}{3} \frac{ε}{1 - ε} d_{p}; d_{h 2} = \frac{ε}{1 - ε} d_{p}

…”

Section: Flow Characteristics In the Pebble Bedmentioning

confidence: 99%

“…Thus in the KTA correlation, the inertial term coefficient decreases with the increasing Reynolds number, Re dh 2 to consider the difference in the transition regime 47 . In the experiment by Liu et al using the high‐Prandtl‐number fluid, Dowtherm A, different forms of correlations were given for the transition and turbulent flow regimes respectively 3 …”

Section: Flow Characteristics In the Pebble Bedmentioning

confidence: 99%

“…Different from the rod‐type fuel in the existing water‐cooled nuclear reactors, the pebble‐type fuel has been adopted in some kinds of the fourth generation nuclear reactors, including the High‐Temperature Gas‐cooled Reactors (HTGRs), 1 Fluoride‐salt‐cooled High‐temperature Reactors (FHRs) 2‐4 and Water‐cooled Pebble Bed Reactors (WPBRs), 5,6 as shown in Table 1. The 6‐cm‐diameter or 3‐cm‐diameter pebble fuels contain fuel‐free graphite zone and the graphite matrix zone, where the microscopic TRIstructural‐iSOtropic (TRISO) coated fuel particles are embedded 1,2 .…”

Section: Introductionmentioning

confidence: 99%

“…To reduce the minimum fluidization velocity and increase the heat transfer performance, Mandal et al proposed the packed fluidized pebble bed design for the fusion breeder blanket, where the smaller pebbles could be fluidized in the void formed by the larger and static pebbles 17‐19 . For the HTGRs, the coolant in the pebble bed reactor core is the high‐temperature gas, helium with Prandtl number at 0.7 at the operation condition, 20 while the FHRs adopt the high‐Prandtl‐number fluoride salts as the coolant (Pr = 14‐20) 3 . The complex geometry formed by the randomly packed pebble bed and different types of coolant make the thermal‐hydraulics in the pebble‐bed‐type reactor core much more complicated than that in the convectional nuclear reactor cores.…”

Section: Introductionmentioning

confidence: 99%

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Review of the experimental research on the thermal‐hydraulic characteristics in the pebble bed nuclear reactor core and fusion breeder blankets

et al. 2020

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Summary Merits in the inherent safety characteristics and multiple applications, cause the pebble‐bed‐type nuclear reactors, including the High‐Temperature Gas‐cooled Reactors, Fluoride‐salt‐cooled High‐temperature Reactors and Water‐cooled Pebble‐bed Reactors, to gain more focus in recent years. Thermal‐hydraulic characteristics in the pebble bed reactor core are of great significance to the safety evaluation and design of such reactors. Experimental investigations on the thermal‐hydraulics of different fluids in the pebble‐bed‐type of nuclear reactor core have been reviewed in this paper. Main experimental methods to determine the flow regime transition, convective heat transfer coefficients, and effective thermal conductivity have been summarized, with the merits and disadvantages discussed. Discussions are given on the main factors that can influence the flow, convective heat transfer and effective thermal conductivity in the pebble bed.

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Section: Flow Characteristics In the Pebble Bedmentioning

confidence: 99%

“…One factor that contributed to the difference was the different choice of fluid velocity and characteristic length. Definitions of the Reynolds number are as follows 3,24‐27,31 :

\begin{matrix} centertrue \\ Re = \frac{ρ {italicud}_{p}}{μ}; {italicRe}_{p 1} = \frac{ρ {italicud}_{p}}{μ}; {italicRe}_{p 2} = \frac{ρ u_{p} d_{p}}{μ} \\ {italicRe}_{dh 1} = \frac{ρ {italicud}_{h 1}}{μ}; {italicRe}_{dh 2} = \frac{ρ u_{p} d_{h 2}}{μ}; {italicRe}_{dh 3} = \frac{ρ u_{p} d_{h 1}}{μ} \end{matrix}

where d p is the pebble diameter; u , the superficial velocity;

d_{p}^{'}

, the pore diameter and u p , the pore velocity. d h 1 and d h 2 are the pebble bed hydraulic diameters, which are defined as follows:

d_{h 1} = \frac{2}{3} \frac{ε}{1 - ε} d_{p}; d_{h 2} = \frac{ε}{1 - ε} d_{p}

…”

Section: Flow Characteristics In the Pebble Bedmentioning

confidence: 99%

Section: Flow Characteristics In the Pebble Bedmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Review of the experimental research on the thermal‐hydraulic characteristics in the pebble bed nuclear reactor core and fusion breeder blankets

et al. 2020

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Numerical investigation of mixed convection of non‐Newtonian fluid in a vented square cavity with fixed baffle

Ghurban,

Al‐Farhany,

Olayemi

2023

Heat Trans

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This paper numerically investigates mixed convective heat transfer in a vented square cavity incorporated with a baffle that is subjected to external non‐Newtonian fluids (NNFs). Adiabatic conditions are imposed on the top and bottom walls, while cold temperature conditions are applied to the right and left solid boundaries. Heated NNF enters the cavity through the inlet and goes out through the outlet at three different locations, and it passes on a vertical baffle fixed at the base placed at different lengths. To examine the impact of the inlet and outlet positions, three different shapes of the outlet port located on the right wall and the inlet port on the left bottom wall were investigated. The impacts of Reynolds number (Re) of 100 ≤ Re ≤ 1000, Richardson number (Ri) of 0.1 ≤ Ri ≤ 3, power law index (n) of 0.6 ≤ n ≤ 1.4, length of baffle (Lb) of 0.2 ≤ Lb ≤ 0.6 and the outlet hole positions (S) of on the thermal and flow distributions in the cavity are taken into consideration in this paper. The results demonstrated that the flow's intensity and heat transfer increase with improvement in the Re and n at any baffle length. When the Ri increased from 0.1 to 3, increased by 23.3% at , and 13.8% at . Also, the Ri increment results in the augmentation of the average heat transfer.

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Introduction

Jiang¹,

Tu²,

Yang³

et al. 2020

Multiphase Flow and Heat Transfer in Pebble Bed Reactor Core

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Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed core

Cited by 32 publications

References 24 publications

Review of the experimental research on the thermal‐hydraulic characteristics in the pebble bed nuclear reactor core and fusion breeder blankets

Review of the experimental research on the thermal‐hydraulic characteristics in the pebble bed nuclear reactor core and fusion breeder blankets

Numerical investigation of mixed convection of non‐Newtonian fluid in a vented square cavity with fixed baffle

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