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Shape and Divertor Control in Tokamaks- [electronic resource]
Shape and Divertor Control in Tokamaks - [electronic resource]
Shape and Divertor Control in Tokamaks- [electronic resource]

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자료유형  
 학위논문파일 국외
최종처리일시  
20240214100439
ISBN  
9798379718497
DDC  
530
저자명  
Wai, Josiah Titus.
서명/저자  
Shape and Divertor Control in Tokamaks - [electronic resource]
발행사항  
[S.l.]: : Princeton University., 2023
발행사항  
Ann Arbor : : ProQuest Dissertations & Theses,, 2023
형태사항  
1 online resource(241 p.)
주기사항  
Source: Dissertations Abstracts International, Volume: 84-12, Section: B.
주기사항  
Advisor: Kolemen, Egemen.
학위논문주기  
Thesis (Ph.D.)--Princeton University, 2023.
사용제한주기  
This item must not be sold to any third party vendors.
초록/해제  
요약As tokamak fusion reactors increase in size and power, robust and high performance technologies will be needed to perform tasks of magnetic control and high heat flux power exhaust. Advanced divertor strategies such as the X-divertor, snowflake, and X-point target divertor have been proposed as candidate solutions for mitigating the enormous power levels experienced in reactors. These advanced divertors are created in part through modification of the magnetic field structure to create and control additional magnetic field nulls. Additionally, the startup, shaping, and vertical control tasks of future reactors will be pushed to hardware limits as machine size and complexity increase. Control techniques that can effectively use the available hardware and optimize performance while satisfying constraints are necessary. Measurement and estimation of various parameters will be more difficult suggesting the usage of models that use inputs from multiple diagnostics or employ neural networks. This thesis explores the physics and engineering challenges of these magnetic control and estimation problems in detail for applications of shape and divertor control in tokamaks.
일반주제명  
Plasma physics.
일반주제명  
Mechanical engineering.
일반주제명  
Applied physics.
키워드  
Divertor
키워드  
Feedback control
키워드  
Neural nets
키워드  
Nuclear fusion
키워드  
Shape control
키워드  
Tokamaks
기타저자  
Princeton University Mechanical and Aerospace Engineering
기본자료저록  
Dissertations Abstracts International. 84-12B.
기본자료저록  
Dissertation Abstract International
전자적 위치 및 접속  
로그인 후 원문을 볼 수 있습니다.

MARC

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■020    ▼a9798379718497
■035    ▼a(MiAaPQ)AAI30491141
■040    ▼aMiAaPQ▼cMiAaPQ
■0820  ▼a530
■1001  ▼aWai,  Josiah  Titus.
■24510▼aShape  and  Divertor  Control  in  Tokamaks▼h[electronic  resource]
■260    ▼a[S.l.]:▼bPrinceton  University.  ▼c2023
■260  1▼aAnn  Arbor  :▼bProQuest  Dissertations  &  Theses,  ▼c2023
■300    ▼a1  online  resource(241  p.)
■500    ▼aSource:  Dissertations  Abstracts  International,  Volume:  84-12,  Section:  B.
■500    ▼aAdvisor:  Kolemen,  Egemen.
■5021  ▼aThesis  (Ph.D.)--Princeton  University,  2023.
■506    ▼aThis  item  must  not  be  sold  to  any  third  party  vendors.
■520    ▼aAs  tokamak  fusion  reactors  increase  in  size  and  power,  robust  and  high  performance  technologies  will  be  needed  to  perform  tasks  of  magnetic  control  and  high  heat  flux  power  exhaust.  Advanced  divertor  strategies  such  as  the  X-divertor,  snowflake,  and  X-point  target  divertor  have  been  proposed  as  candidate  solutions  for  mitigating  the  enormous  power  levels  experienced  in  reactors.  These  advanced  divertors  are  created  in  part  through  modification  of  the  magnetic  field  structure  to  create  and  control  additional  magnetic  field  nulls.  Additionally,  the  startup,  shaping,  and  vertical  control  tasks  of  future  reactors  will  be  pushed  to  hardware  limits  as  machine  size  and  complexity  increase.  Control  techniques  that  can  effectively  use  the  available  hardware  and  optimize  performance  while  satisfying  constraints  are  necessary.  Measurement  and  estimation  of  various  parameters  will  be  more  difficult  suggesting  the  usage  of  models  that  use  inputs  from  multiple  diagnostics  or  employ  neural  networks.  This  thesis  explores  the  physics  and  engineering  challenges  of  these  magnetic  control  and  estimation  problems  in  detail  for  applications  of  shape  and  divertor  control  in  tokamaks.
■590    ▼aSchool  code:  0181.
■650  4▼aPlasma  physics.
■650  4▼aMechanical  engineering.
■650  4▼aApplied  physics.
■653    ▼aDivertor
■653    ▼aFeedback  control
■653    ▼aNeural  nets
■653    ▼aNuclear  fusion
■653    ▼aShape  control
■653    ▼aTokamaks
■690    ▼a0759
■690    ▼a0548
■690    ▼a0215
■71020▼aPrinceton  University▼bMechanical  and  Aerospace  Engineering.
■7730  ▼tDissertations  Abstracts  International▼g84-12B.
■773    ▼tDissertation  Abstract  International
■790    ▼a0181
■791    ▼aPh.D.
■792    ▼a2023
■793    ▼aEnglish
■85640▼uhttp://www.riss.kr/pdu/ddodLink.do?id=T16932296▼nKERIS▼z이  자료의  원문은  한국교육학술정보원에서  제공합니다.
■980    ▼a202402▼f2024

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