Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride Salt Cooled High Temperature Test ReactorSource: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 001::page 11003DOI: 10.1115/1.4026391Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The 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.
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contributor author | Cheng, Wen | |
contributor author | Sun, Kaichao | |
contributor author | Hu, Lin | |
contributor author | Chieng, Ching | |
date accessioned | 2017-05-09T01:22:15Z | |
date available | 2017-05-09T01:22:15Z | |
date issued | 2015 | |
identifier issn | 2332-8983 | |
identifier other | NERS_1_1_011003.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl/handle/yetl/159277 | |
description abstract | The 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. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride Salt Cooled High Temperature Test Reactor | |
type | Journal Paper | |
journal volume | 1 | |
journal issue | 1 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4026391 | |
journal fristpage | 11003 | |
journal lastpage | 11003 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 001 | |
contenttype | Fulltext |