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Coupled neutronic-thermal-hydraulic analysis of a small FHR core with pin-type fuel assemblies

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dc.citedby2
dc.contributor.authorMohamed H.en_US
dc.contributor.authorKotlyar D.en_US
dc.contributor.authorParks G.en_US
dc.contributor.authorShaposhnik Y.en_US
dc.contributor.authorid57136356100en_US
dc.contributor.authorid45661217600en_US
dc.contributor.authorid7103057721en_US
dc.contributor.authorid51261305700en_US
dc.date.accessioned2023-05-29T06:13:31Z
dc.date.available2023-05-29T06:13:31Z
dc.date.issued2016
dc.descriptionFluorine compounds; High temperature reactors; Sensitivity analysis; Coolant temperature; Discharge burn-up; External coupling; Fuel assembly design; High temperature; Reactor physics; Thermal hydraulics; Thermal-hydraulic analysis; Fuelsen_US
dc.description.abstractThis study undertook a coupled neutronic-thermal-hydraulic analysis of a small fluoride salt-cooled high-temperature reactor (FHR), one of the advanced Gen. IV concepts. The objective is to further investigate the practical feasibility of two UO2 pin-type fuel assembly designs, namely 3- and 4-ring designs, by looking primarily at thermal-hydraulic (TH) parameters, such as linear power and fuel centreline temperature, as well as radial power peaking. The coupled neutronic-TH analysis was performed by the external coupling of Serpent, a Monte Carlo based reactor physics code, with the TH feedback provided by THERMO. Sensitivity analysis was performed by varying the fuel pin radius by �5% and �10% of its original size. Results show that the 4-ring design has better TH performance than the 3-ring design. However, this TH advantage is outweighed by the superior ncutronic performance offered by the 3-ring design. The change in fuel pin radius docs not significantly affect fuel centreline and coolant temperatures for either design, but the discharge burnup and pressure drop increase with increasing fuel pin radius.en_US
dc.description.natureFinalen_US
dc.identifier.epage2639
dc.identifier.scopus2-s2.0-84992123224
dc.identifier.spage2630
dc.identifier.urihttps://www.scopus.com/inward/record.uri?eid=2-s2.0-84992123224&partnerID=40&md5=88f8270d62c6304d50f659162eec764b
dc.identifier.urihttps://irepository.uniten.edu.my/handle/123456789/22936
dc.identifier.volume4
dc.publisherAmerican Nuclear Societyen_US
dc.sourceScopus
dc.sourcetitlePhysics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century
dc.titleCoupled neutronic-thermal-hydraulic analysis of a small FHR core with pin-type fuel assembliesen_US
dc.typeConference Paperen_US
dspace.entity.typePublication
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