Immersed boundary—thermal lattice Boltzmann method for the moving simulation of non-isothermal elliptical particles

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Author listKarimnejad S., Amiri Delouei A., Nazari M., Shahmardan M.M., Rashidi M.M., Wongwises S.

PublisherElsevier

Publication year2019

JournalNuclear Engineering and Technology (1738-5733)

Volume number138

Issue number6

Start page4003

End page4017

Number of pages15

ISSN1738-5733

eISSN1738-5733

URLhttps://www.scopus.com/inward/record.uri?eid=2-s2.0-85078714734&doi=10.1016%2fj.net.2020.01.005&partnerID=40&md5=edeac5522674ffaecadedca6f4ac8221

LanguagesEnglish-Great Britain (EN-GB)


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Abstract

We propose a scaled-down experimental model of vertical air-natural convection channels by applying the modified Ishii–Kataoka scaling method with the assistance of numerical analyses to the Reactor Vault Cooling System (RVCS) of the Proto-type Gen-IV Sodium-cooled fast reactor (PGSFR) being developed in Korea. Two major non-dimensional numbers (modified Richardson and Friction number) from the momentum equation and Stanton number from the energy balance equation were identified to design the scaled-down experimental model to assimilate thermal-hydraulic behaviors of the natural convective air-cooling channel of RVCS. The ratios of the design parameters in the PGSFR RVCS between the prototype and the scaled-down model were determined by setting Richardson and Stanton number to be unity. The friction number which cannot be determined by the Ishii-Kataoka method was estimated by numerical analyses using the MARS-KS system code. The numerical analyses showed that the friction number with the form loss coefficient of 2.0 in the scale-down model would result in an acceptable prediction of the thermal-hydraulic behavior in RVCS. We also performed experimental benchmarking using the scaled-down model with the MARS-KS simulations to verify the appropriateness of the scale-down model, which demonstrated that the temperature rises and the average air flow velocity measured in the scale-down model. © 2020 Korean Nuclear Society


Keywords

Asymmetric heatingRVCSScaling analysisVertical parallel plate


Last updated on 2023-04-10 at 07:37