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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 React...
Time Dependent Full Core Coupled Multiphysics Analysis of Nuclear Thermal Propulsion Reactors

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자료유형  
 학위논문 서양
최종처리일시  
20260202105539
ISBN  
9798263391294
DDC  
532
저자명  
Krecicki, Matthew Andrew.
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
기타저자  
Georgia Institute of Technology.
기본자료저록  
Dissertations Abstracts International. 87-05A.
전자적 위치 및 접속  
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MARC

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■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.

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