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Shape and Divertor Control in Tokamaks- [electronic resource]
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Shape and Divertor Control in Tokamaks- [electronic resource]
Detailed Information
- Material Type
- 단행본
- 0016932296
- Date and Time of Latest Transaction
- 20240214100439
- ISBN
- 9798379718497
- DDC
- 530
- Author
- Wai, Josiah Titus.
- Title/Author
- Shape and Divertor Control in Tokamaks - [electronic resource]
- Publish Info
- [S.l.]: : Princeton University., 2023
- Publish Info
- Ann Arbor : : ProQuest Dissertations & Theses,, 2023
- Material Info
- 1 online resource(241 p.)
- General Note
- Source: Dissertations Abstracts International, Volume: 84-12, Section: B.
- General Note
- Advisor: Kolemen, Egemen.
- 학위논문주기
- Thesis (Ph.D.)--Princeton University, 2023.
- Restrictions on Access Note
- This item must not be sold to any third party vendors.
- Abstracts/Etc
- 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.
- Subject Added Entry-Topical Term
- Plasma physics.
- Subject Added Entry-Topical Term
- Mechanical engineering.
- Subject Added Entry-Topical Term
- Applied physics.
- Index Term-Uncontrolled
- Divertor
- Index Term-Uncontrolled
- Feedback control
- Index Term-Uncontrolled
- Neural nets
- Index Term-Uncontrolled
- Nuclear fusion
- Index Term-Uncontrolled
- Shape control
- Index Term-Uncontrolled
- Tokamaks
- Added Entry-Corporate Name
- Princeton University Mechanical and Aerospace Engineering
- Host Item Entry
- Dissertations Abstracts International. 84-12B.
- Host Item Entry
- Dissertation Abstract International
- Electronic Location and Access
- 로그인 후 원문을 볼 수 있습니다.
- 소장사항
-
202402 2024
MARC
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■00520240214100439
■006m o d
■007cr#unu||||||||
■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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