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Fluid Flow and Heat Transfer Characteristics of High Prandtl Number Fluids for Fluoride-Salt-Cooled Reactor Applications
Fluid Flow and Heat Transfer Characteristics of High Prandtl Number Fluids for Fluoride-Sa...
Fluid Flow and Heat Transfer Characteristics of High Prandtl Number Fluids for Fluoride-Salt-Cooled Reactor Applications

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자료유형  
 학위논문 서양
최종처리일시  
20260202105508
ISBN  
9798263326012
DDC  
660
저자명  
Ragoowansi, Evan Ashvin.
서명/저자  
Fluid Flow and Heat Transfer Characteristics of High Prandtl Number Fluids for Fluoride-Salt-Cooled Reactor Applications
발행사항  
[Sl] : Georgia Institute of Technology, 2025
발행사항  
Ann Arbor : ProQuest Dissertations & Theses, 2025
형태사항  
213 p
주기사항  
Source: Dissertations Abstracts International, Volume: 87-05, Section: B.
주기사항  
Advisor: Garimella, Srinivas.
학위논문주기  
Thesis (Ph.D.)--Georgia Institute of Technology, 2025.
초록/해제  
요약Fluoride-salt-cooled high-temperature reactors (FHRs) are a new and developing class of reactors that features low-pressure liquid fluoride salt cooling and the graphitematrix coated-particle fuel developed for high temperature gas reactors (HTGRs) and are designed for a high-temperature power cycle. FHRs have several economic and safety benefits due to higher core power densities compared to HTGRs: near-atmospheric pressure operation, higher safety margins for fuel failure and coolant boiling, and passive decay heat removal using natural circulation. One of the potential fuel designs for FHRs is the plate type configuration in which the molten salt coolant flows in the wide, narrow channels between the array of parallel fuel plates.To aid the further development of FHR designs that employ a plate-type fuel design, this work addresses the need to improve the understanding of the fluid flow dynamics and heat transfer characteristics for a molten salt coolant. The nature of the molten salt requires the flow to be in the transition regime, making predictions based on the literature difficult. In the present study, a test section representing a single coolant channel is designed and fabricated, and a heat transfer test facility is fabricated to measure the heat transfer coefficient and frictional pressure gradient of a surrogate fluid that matches the pertinent dimensionless parameters of molten salt in a plate-type FHR. In addition to the plain coolant channel, a channel with lozenge-shaped dimple features is also developed to study potential heat transfer enhancement. Based on these experimental results, models are developed to predict the heat transfer and pressure drop for such flows experienced in the plate-type FHR. These models are compared with a steady state computational fluid dynamics (CFD) model and a model developed in the thermalhydraulic program TRACE for a single coolant channel. The experimental study serves as a preliminary verification of the models that use CFD and TRACE. The correlations developed in this study are then used to estimate the temperatures in the core and the overall cooling capacity, demonstrating the benefits of an FHR over conventional reactors. Insights from these experiments and analyses will guide the further development of platetype FHRs by improving the confidence levels in the predictions of safety analysis codes, thereby assisting the licensing of these reactors.
일반주제명  
Cold
일반주제명  
Fluid dynamics
일반주제명  
Water
일반주제명  
Fluorides
일반주제명  
Industrial plant emissions
일반주제명  
Friction
일반주제명  
Nuclear energy
일반주제명  
Nuclear reactors
일반주제명  
Cooling
일반주제명  
Viscosity
일반주제명  
Electricity
일반주제명  
Heat exchangers
일반주제명  
Carbon
일반주제명  
Design
일반주제명  
Salt
일반주제명  
Alternative energy sources
일반주제명  
Reynolds number
일반주제명  
Geometry
일반주제명  
Hydraulics
일반주제명  
Alternative energy
일반주제명  
Atmospheric sciences
일반주제명  
Fluid mechanics
일반주제명  
Nuclear engineering
일반주제명  
Nuclear physics
일반주제명  
Thermodynamics
기타저자  
Georgia Institute of Technology.
기본자료저록  
Dissertations Abstracts International. 87-05B.
전자적 위치 및 접속  
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MARC

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■1001  ▼aRagoowansi,  Evan  Ashvin.
■24510▼aFluid  Flow  and  Heat  Transfer  Characteristics  of  High  Prandtl  Number  Fluids  for  Fluoride-Salt-Cooled  Reactor  Applications
■260    ▼a[Sl]▼bGeorgia  Institute  of  Technology▼c2025
■260  1▼aAnn  Arbor▼bProQuest  Dissertations  &  Theses▼c2025
■300    ▼a213  p
■500    ▼aSource:  Dissertations  Abstracts  International,  Volume:  87-05,  Section:  B.
■500    ▼aAdvisor:  Garimella,  Srinivas.
■5021  ▼aThesis  (Ph.D.)--Georgia  Institute  of  Technology,  2025.
■520    ▼aFluoride-salt-cooled  high-temperature  reactors  (FHRs)  are  a  new  and  developing  class  of  reactors  that  features  low-pressure  liquid  fluoride  salt  cooling  and  the  graphitematrix  coated-particle  fuel  developed  for  high  temperature  gas  reactors  (HTGRs)  and  are  designed  for  a  high-temperature  power  cycle.  FHRs  have  several  economic  and  safety  benefits  due  to  higher  core  power  densities  compared  to  HTGRs:  near-atmospheric  pressure  operation,  higher  safety  margins  for  fuel  failure  and  coolant  boiling,  and  passive  decay  heat  removal  using  natural  circulation.  One  of  the  potential  fuel  designs  for  FHRs  is  the  plate  type  configuration  in  which  the  molten  salt  coolant  flows  in  the  wide,  narrow  channels  between  the  array  of  parallel  fuel  plates.To  aid  the  further  development  of  FHR  designs  that  employ  a  plate-type  fuel  design,  this  work  addresses  the  need  to  improve  the  understanding  of  the  fluid  flow  dynamics  and  heat  transfer  characteristics  for  a  molten  salt  coolant.  The  nature  of  the  molten  salt  requires  the  flow  to  be  in  the  transition  regime,  making  predictions  based  on  the  literature  difficult.  In  the  present  study,  a  test  section  representing  a  single  coolant  channel  is  designed  and  fabricated,  and  a  heat  transfer  test  facility  is  fabricated  to  measure  the  heat  transfer  coefficient  and  frictional  pressure  gradient  of  a  surrogate  fluid  that  matches  the  pertinent  dimensionless  parameters  of  molten  salt  in  a  plate-type  FHR.  In  addition  to  the  plain  coolant  channel,  a  channel  with  lozenge-shaped  dimple  features  is  also  developed  to  study  potential  heat  transfer  enhancement.  Based  on  these  experimental  results,  models  are  developed  to  predict  the  heat  transfer  and  pressure  drop  for  such  flows  experienced  in  the  plate-type  FHR.  These  models  are  compared  with  a  steady  state  computational  fluid  dynamics  (CFD)  model  and  a  model  developed  in  the  thermalhydraulic  program  TRACE  for  a  single  coolant  channel.  The  experimental  study  serves  as  a  preliminary  verification  of  the  models  that  use  CFD  and  TRACE.  The  correlations  developed  in  this  study  are  then  used  to  estimate  the  temperatures  in  the  core  and  the  overall  cooling  capacity,  demonstrating  the  benefits  of  an  FHR  over  conventional  reactors.  Insights  from  these  experiments  and  analyses  will  guide  the  further  development  of  platetype  FHRs  by  improving  the  confidence  levels  in  the  predictions  of  safety  analysis  codes,  thereby  assisting  the  licensing  of  these  reactors.
■590    ▼aSchool  code:  0078.
■650  4▼aCold
■650  4▼aFluid  dynamics
■650  4▼aWater
■650  4▼aFluorides
■650  4▼aIndustrial  plant  emissions
■650  4▼aFriction
■650  4▼aNuclear  energy
■650  4▼aNuclear  reactors
■650  4▼aCooling
■650  4▼aViscosity
■650  4▼aElectricity
■650  4▼aHeat  exchangers
■650  4▼aCarbon
■650  4▼aDesign
■650  4▼aSalt
■650  4▼aAlternative  energy  sources
■650  4▼aReynolds  number
■650  4▼aGeometry
■650  4▼aHydraulics
■650  4▼aAlternative  energy
■650  4▼aAtmospheric  sciences
■650  4▼aFluid  mechanics
■650  4▼aNuclear  engineering
■650  4▼aNuclear  physics
■650  4▼aThermodynamics
■690    ▼a0389
■690    ▼a0363
■690    ▼a0725
■690    ▼a0204
■690    ▼a0552
■690    ▼a0756
■690    ▼a0348
■71020▼aGeorgia  Institute  of  Technology.
■7730  ▼tDissertations  Abstracts  International▼g87-05B.
■790    ▼a0078
■791    ▼aPh.D.
■792    ▼a2025
■793    ▼aEnglish
■85640▼uhttp://www.riss.kr/pdu/ddodLink.do?id=T17360334▼nKERIS▼z이  자료의  원문은  한국교육학술정보원에서  제공합니다.

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