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contributor authorCheng, Wen
contributor authorSun, Kaichao
contributor authorHu, Lin
contributor authorChieng, Ching
date accessioned2017-05-09T01:22:15Z
date available2017-05-09T01:22:15Z
date issued2015
identifier issn2332-8983
identifier otherNERS_1_1_011003.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/159277
description abstractThe fluoridesaltcooled hightemperature reactor (FHR) is an advanced reactor concept that uses tristructural isotropic (TRISO) hightemperature fuel and lowpressure liquid salt coolant. A 20MWth test reactor, as the key step in demonstrating the technical feasibility, is currently under design at Massachusetts Institute of Technology. This study focuses on the coupled conduction and convection heat transfer adopting a threedimensional unitcell model with one coolant channel and six onethird fuel compacts. The laminar, transitional, and turbulent flows are investigated with the use of computational fluid dynamic (CFD) software, CDadapco STARCCM+. The model is validated against theory for developing laminar flow in the benchmark study with excellent agreement. The model is also benchmarked for transitional and turbulent flows by Hausen, Gnielinski, DittusBoelter, and SiederTate correlations. Azimuthal distributions of temperature, heat flux, and heat transfer coefficient along the coolantgraphite interface were obtained for the asymmetric heat source, graphite materials, and two different types of salt coolant. The results show that the asymmetric power generation has little impact on peak fuel temperature, interface temperature, and heat transfer coefficient for a unitcell module in laminar flow regime due to effective thermal conduction of the graphite matrix. In the turbulent flow regime, the effect on the azimuthal heat flux and heat transfer coefficient is more pronounced.
publisherThe American Society of Mechanical Engineers (ASME)
titleComputational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride Salt Cooled High Temperature Test Reactor
typeJournal Paper
journal volume1
journal issue1
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4026391
journal fristpage11003
journal lastpage11003
treeJournal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 001
contenttypeFulltext


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