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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-Salt-Cooled Reactor Applications
상세정보
- 자료유형
- 학위논문 서양
- 최종처리일시
- 20260202105508
- ISBN
- 9798263326012
- DDC
- 660
- 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
- Friction
- 일반주제명
- Nuclear energy
- 일반주제명
- Nuclear reactors
- 일반주제명
- Cooling
- 일반주제명
- Viscosity
- 일반주제명
- Electricity
- 일반주제명
- Heat exchangers
- 일반주제명
- Carbon
- 일반주제명
- Design
- 일반주제명
- Salt
- 일반주제명
- Reynolds number
- 일반주제명
- Geometry
- 일반주제명
- Hydraulics
- 일반주제명
- Alternative energy
- 일반주제명
- Atmospheric sciences
- 일반주제명
- Fluid mechanics
- 일반주제명
- Nuclear engineering
- 일반주제명
- Nuclear physics
- 일반주제명
- Thermodynamics
- 기본자료저록
- Dissertations Abstracts International. 87-05B.
- 전자적 위치 및 접속
- 로그인 후 원문을 볼 수 있습니다.
MARC
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■00520260202105508
■006m o d
■007cr#unu||||||||
■020 ▼a9798263326012
■035 ▼a(MiAaPQ)AAI32308073
■035 ▼a(MiAaPQ)GeorgiaTech78640
■040 ▼aMiAaPQ▼cMiAaPQ
■0820 ▼a660
■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.


