Characteristics of convective heat transport in a packed pebble-bed reactor

Abdulmohsin, Rahman S.; Al‐Dahhan, Muthanna H.

doi:10.1016/j.nucengdes.2014.11.041

Cited by 45 publications

(10 citation statements)

References 19 publications

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“…The efficiency of the pebble-bed reactor is dependent upon how the coolant removes the generated heat from the dynamic core of this reactor. Therefore, to reliably simulate the thermalhydraulic phenomena, and hence the performance in the dynamic core of nuclear packed-pebble bed reactors, the coolant gas dynamics and heat transport processes must be characterized (Abdulmohsin and Al-Dahhan, 2011a;2011b;2012). In addition, the experimental investigation of the thermal-hydraulic characteristics of pebble beds is an issue of high importance when selecting the core geometry and evaluating the performance and safety of such types of reactors (Rimkevicius and Uspuras, 2008).…”

Section: Introductionmentioning

confidence: 99%

Axial dispersion and mixing phenomena of the gas phase in a packed pebble-bed reactor

Abdulmohsin

Al‐Dahhan

2016

Annals of Nuclear Energy

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Section: Introductionmentioning

confidence: 99%

Axial dispersion and mixing phenomena of the gas phase in a packed pebble-bed reactor

Abdulmohsin

Al‐Dahhan

2016

Annals of Nuclear Energy

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“…The local convective heat transfer coefficients as well as radial profiles were measured experimentally using a sophisticated noninvasive heat transfer probe (Abdulmohsin and Al-Dahhan, 2015). The effect of gas velocity on the heat transfer coefficient was investigated over a wide range of Reynolds numbers.…”

Section: =mentioning

confidence: 99%

A review of pebble flow study for pebble bed high temperature gas-cooled reactor

Jiang

Yang

et al. 2019

Exp. Comput. Multiph. Flow

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The pebble bed high temperature gas-cooled reactor is a promising generation-IV reactor, which uses large fuel pebbles and helium gas as coolant. The pebble bed flow is a fundamental issue for both academic investigation and engineering application, e.g., reactor core design and safety analysis. This work performed a review of recent progress on pebble flow study, focusing on the important issues like pebble flow, gas phase hydrodynamics, and inter-phase heat transfer (thermal hydraulics). Our group's researches on pebble flow have also been reviewed through the aspects of phenomenological observation and measurement, voidage distribution, geometric and parameter optimization, pebble flow mechanisms, flow regime categorization, and fundamentals of modelings of pebble flow and radiation. Finally, the major problems or possible directions of research are concluded which would be some of our focuses on the pebble bed flow study.

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“…Based on this type of method, Abdulmohsin and Al‐Dahhan adopted a pebble‐type noninvasive heat transfer probe to obtain the local convective heat transfer coefficients in the reactor core of VHTRs 60 . As shown in Figure 9, the cartridge heater was installed inside the cooper pebble to provide internal heat generation.…”

Section: Convective Heat Transfer Characteristics In the Packed Pebble Bedmentioning

confidence: 99%

“…A heat flux sensor was mounted on the pebble surface, to measure the heat flux and surface temperature instantaneously. Air temperatures were obtained by the thermocouples installed adjacent to the heat transfer probe 60 …”

Section: Convective Heat Transfer Characteristics In the Packed Pebble Bedmentioning

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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Characteristics of convective heat transport in a packed pebble-bed reactor

Cited by 45 publications

References 19 publications

Axial dispersion and mixing phenomena of the gas phase in a packed pebble-bed reactor

Axial dispersion and mixing phenomena of the gas phase in a packed pebble-bed reactor

A review of pebble flow study for pebble bed high temperature gas-cooled reactor

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

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