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Time Dependent Full Core Coupled Multiphysics Analysis of Nuclear Thermal Propulsion Reactors
Time Dependent Full Core Coupled Multiphysics Analysis of Nuclear Thermal Propulsion Reactors
상세정보
- 자료유형
- 학위논문 서양
- 최종처리일시
- 20260202105539
- ISBN
- 9798263391294
- DDC
- 532
- 서명/저자
- Time Dependent Full Core Coupled Multiphysics Analysis of Nuclear Thermal Propulsion Reactors
- 발행사항
- [Sl] : Georgia Institute of Technology, 2023
- 발행사항
- Ann Arbor : ProQuest Dissertations & Theses, 2023
- 형태사항
- 194 p
- 주기사항
- Source: Dissertations Abstracts International, Volume: 87-05, Section: A.
- 주기사항
- Advisor: Kotlyar, Dan;Petrovic, Bojan.
- 학위논문주기
- Thesis (Ph.D.)--Georgia Institute of Technology, 2023.
- 초록/해제
- 요약A novel full-core multiphysics analysis framework for Nuclear Thermal Propulsion (NTP) Reactors is developed in this dissertation. To achieve the high specific impulses and thrust levels required for crewed space exploration missions NTP systems operate at very high temperatures, rely on complex counter-flow needed to drive the turbopump, and exhibit dynamic behavior for short pulse-like operation. Therefore, the design and analysis of a NTP reactor-core requires multiphysics computational tools that can capture the heat transfer and flow complexities and dynamic haviour during the engine operation. Existing higher-order codes, such as ANSYS, can analyze complex flow paths in a NTP reactor, but incur prohibitively large computational costs and are not applicable for full-core multiphysics analysis. The development and verification of the reduced-order, ntpThermo, code is a novel contribution as it is capable of accurately modeling the complex flow paths and heat transfer within an NTP reactor. In addition, ntpThermo can perform coupled thermal-hydraulic thermo-mechanical analysis to capture the impact of thermal expansion with an acceptable computational cost. The ntpThermo code is coupled to the Monte Carlo Neutron transport Serpent code via the novel Basilisk multiphysics framework. The Basilisk framework enables full-core time-dependent multiphysics analysis by leveraging the pre-existing depletion solvers implemented into the Serpent code. The framework also enables the user to perform a critical drum search during each depletion step to account for the impact of control drum rotation during operation.Previous NTP-related research that focused on full core design has applied decoupled analysis approaches where the impact of thermal-hydraulic and thermo-mechanical feedback on the neutronic solution is neglected. In an effort to provide useful insights for current programs a reactor design which adheres to the current industry ground rules was developed. The subsequent analysis demonstrates that such decoupled approaches can introduce significant errors in the spatial power distributions and thus predicted thermal and mechanical safety margins. More specifically, for heavily moderated High Assay-Low Enriched Uranium fueled designs the fuel and moderator temperature spatial distributions have a significant impact on the neutron economy and spatial power distributions. Additionally, the impact of thermo-mechanical feedback has a significant impact on the mass-flow distribution within the core, and thus the solid material temperatures. Due to the elevated exit gas temperatures required to satisfy rocket engine performance requirements orificing is typically applied to the fuel elements in the core to reduce peak fuel temperatures. When a consistent multiphysics design approach is applied to design the orificing pattern a constant peak fuel temperature can be maintained through a 60-minute full-power burn due to the balance of various multiphysics feedback mechanisms. This dissertation demonstrates the importance of multiphysics tools to design a NTP reactor that can maintain adequate thermal and mechanical safety margins while also satisfying engine performance requirements.
- 일반주제명
- Fluid dynamics
- 일반주제명
- Pressure vessels
- 일반주제명
- Zirconium
- 일반주제명
- High temperature
- 일반주제명
- Hydrogen
- 일반주제명
- Codes
- 일반주제명
- Engines
- 일반주제명
- Aerospace engineering
- 일반주제명
- Boundary conditions
- 일반주제명
- Engineers
- 일반주제명
- Corrosion
- 일반주제명
- Heat transfer
- 일반주제명
- Turbines
- 일반주제명
- Nuclear reactors
- 일반주제명
- Beryllium
- 일반주제명
- Uranium
- 일반주제명
- Moon
- 일반주제명
- Medical research
- 일반주제명
- Design
- 일반주제명
- Hydraulics
- 일반주제명
- Fluid mechanics
- 일반주제명
- Mathematics
- 일반주제명
- Medicine
- 일반주제명
- Nuclear engineering
- 일반주제명
- Thermodynamics
- 기본자료저록
- Dissertations Abstracts International. 87-05A.
- 전자적 위치 및 접속
- 로그인 후 원문을 볼 수 있습니다.
MARC
008260126s2023 us c eng d■001000017360515
■00520260202105539
■006m o d
■007cr#unu||||||||
■020 ▼a9798263391294
■035 ▼a(MiAaPQ)AAI32315061
■035 ▼a(MiAaPQ)GeorgiaTech72007
■040 ▼aMiAaPQ▼cMiAaPQ
■0820 ▼a532
■1001 ▼aKrecicki, Matthew Andrew.
■24510▼aTime Dependent Full Core Coupled Multiphysics Analysis of Nuclear Thermal Propulsion Reactors
■260 ▼a[Sl]▼bGeorgia Institute of Technology▼c2023
■260 1▼aAnn Arbor▼bProQuest Dissertations & Theses▼c2023
■300 ▼a194 p
■500 ▼aSource: Dissertations Abstracts International, Volume: 87-05, Section: A.
■500 ▼aAdvisor: Kotlyar, Dan;Petrovic, Bojan.
■5021 ▼aThesis (Ph.D.)--Georgia Institute of Technology, 2023.
■520 ▼aA novel full-core multiphysics analysis framework for Nuclear Thermal Propulsion (NTP) Reactors is developed in this dissertation. To achieve the high specific impulses and thrust levels required for crewed space exploration missions NTP systems operate at very high temperatures, rely on complex counter-flow needed to drive the turbopump, and exhibit dynamic behavior for short pulse-like operation. Therefore, the design and analysis of a NTP reactor-core requires multiphysics computational tools that can capture the heat transfer and flow complexities and dynamic haviour during the engine operation. Existing higher-order codes, such as ANSYS, can analyze complex flow paths in a NTP reactor, but incur prohibitively large computational costs and are not applicable for full-core multiphysics analysis. The development and verification of the reduced-order, ntpThermo, code is a novel contribution as it is capable of accurately modeling the complex flow paths and heat transfer within an NTP reactor. In addition, ntpThermo can perform coupled thermal-hydraulic thermo-mechanical analysis to capture the impact of thermal expansion with an acceptable computational cost. The ntpThermo code is coupled to the Monte Carlo Neutron transport Serpent code via the novel Basilisk multiphysics framework. The Basilisk framework enables full-core time-dependent multiphysics analysis by leveraging the pre-existing depletion solvers implemented into the Serpent code. The framework also enables the user to perform a critical drum search during each depletion step to account for the impact of control drum rotation during operation.Previous NTP-related research that focused on full core design has applied decoupled analysis approaches where the impact of thermal-hydraulic and thermo-mechanical feedback on the neutronic solution is neglected. In an effort to provide useful insights for current programs a reactor design which adheres to the current industry ground rules was developed. The subsequent analysis demonstrates that such decoupled approaches can introduce significant errors in the spatial power distributions and thus predicted thermal and mechanical safety margins. More specifically, for heavily moderated High Assay-Low Enriched Uranium fueled designs the fuel and moderator temperature spatial distributions have a significant impact on the neutron economy and spatial power distributions. Additionally, the impact of thermo-mechanical feedback has a significant impact on the mass-flow distribution within the core, and thus the solid material temperatures. Due to the elevated exit gas temperatures required to satisfy rocket engine performance requirements orificing is typically applied to the fuel elements in the core to reduce peak fuel temperatures. When a consistent multiphysics design approach is applied to design the orificing pattern a constant peak fuel temperature can be maintained through a 60-minute full-power burn due to the balance of various multiphysics feedback mechanisms. This dissertation demonstrates the importance of multiphysics tools to design a NTP reactor that can maintain adequate thermal and mechanical safety margins while also satisfying engine performance requirements.
■590 ▼aSchool code: 0078.
■650 4▼aFluid dynamics
■650 4▼aPressure vessels
■650 4▼aZirconium
■650 4▼aHigh temperature
■650 4▼aHydrogen
■650 4▼aCodes
■650 4▼aEngines
■650 4▼aAerospace engineering
■650 4▼aBoundary conditions
■650 4▼aEngineers
■650 4▼aCorrosion
■650 4▼aHeat transfer
■650 4▼aTurbines
■650 4▼aNuclear reactors
■650 4▼aBeryllium
■650 4▼aUranium
■650 4▼aMoon
■650 4▼aMedical research
■650 4▼aDesign
■650 4▼aHydraulics
■650 4▼aFluid mechanics
■650 4▼aMathematics
■650 4▼aMedicine
■650 4▼aNuclear engineering
■650 4▼aThermodynamics
■690 ▼a0389
■690 ▼a0538
■690 ▼a0204
■690 ▼a0405
■690 ▼a0564
■690 ▼a0552
■690 ▼a0348
■71020▼aGeorgia Institute of Technology.
■7730 ▼tDissertations Abstracts International▼g87-05A.
■790 ▼a0078
■791 ▼aPh.D.
■792 ▼a2023
■793 ▼aEnglish
■85640▼uhttp://www.riss.kr/pdu/ddodLink.do?id=T17360515▼nKERIS▼z이 자료의 원문은 한국교육학술정보원에서 제공합니다.


