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Feasibility study of neutral beam injection in Thailand Tokamak-1

http://hdl.handle.net/10655/00013537
http://hdl.handle.net/10655/00013537
c752ae86-63dc-40ed-a3bd-0d7f8e344867
名前 / ファイル ライセンス アクション
13310_Fusion.Eng.Des.pdf 13310_Fusion.Eng.Des (1.3 MB)
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Item type 学術雑誌論文 / Journal Article(1)
公開日 2023-01-10
タイトル
タイトル Feasibility study of neutral beam injection in Thailand Tokamak-1
言語
言語 eng
キーワード
主題Scheme Other
主題 Thailand -1
キーワード
主題Scheme Other
主題 Fast ion
キーワード
主題Scheme Other
主題 Lorentz orbit code
キーワード
主題Scheme Other
主題 Neutral beam injection
資源タイプ
資源タイプ識別子 http://purl.org/coar/resource_type/c_6501
資源タイプ journal article
著者 SANGAROON, Siriyaporn

× SANGAROON, Siriyaporn

SANGAROON, Siriyaporn

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OGAWA, Kunihiro

× OGAWA, Kunihiro

OGAWA, Kunihiro

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ISOBE, Mitsutaka

× ISOBE, Mitsutaka

ISOBE, Mitsutaka

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WISITSORASAK, Apiwat

× WISITSORASAK, Apiwat

WISITSORASAK, Apiwat

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PAENTHONG, Worathat

× PAENTHONG, Worathat

PAENTHONG, Worathat

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PROMPING, Jiraporn

× PROMPING, Jiraporn

PROMPING, Jiraporn

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POOLYARAT, N.

× POOLYARAT, N.

POOLYARAT, N.

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TAMMAN, A.

× TAMMAN, A.

TAMMAN, A.

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PLOYKRACHANG, K.

× PLOYKRACHANG, K.

PLOYKRACHANG, K.

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DANGTIP, S.

× DANGTIP, S.

DANGTIP, S.

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ONJUN, T.

× ONJUN, T.

ONJUN, T.

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著者ID
内容記述タイプ Other
内容記述 0000-0002-0160-0468
抄録
内容記述タイプ Abstract
内容記述 Thailand Institute of Nuclear Technology (TINT) is developing Thailand- 1 (TT-1) from a former device HT-6 M of China. The first hydrogen plasma will be initiated in 2023. To investigate high-β plasma and physics related to fast ions, TT-1 will be equipped with auxiliary heating systems. In this work, a feasibility study for installing a neutral beam injection (NBI) heating system in TT-1 is carried out. This work is motivated to characterize beam ion's orbits in different injection angles and to explore a condition suitable in terms of higher heating efficiency. In this work, we assume that a hydrogen beam will be launched into the TT-1 plasma with an acceleration voltage of 20 kV. The orbit simulations using the gyromotion following code LORBIT are performed in various magnetic field equilibria, i.e., different plasma current (Ip), toroidal magnetic field strength (Bt), and the magnetic axis (Rax). Furthermore, beam ions are injected in different directions, i.e., tangential co-injection and tangential counter-injection. In the case of co-injection, beam ion loss is not significant, by about 6%, whereas beam ion loss fraction is evaluated to be 26–34% in the case of counter-injection. Also, it is found that the number of lost beam ions is significantly affected by changing Ip and Rax. The results obtained in this work will directly support the experiment plan for the high-performance plasmas, design of the fast-ion diagnostic system, and systematic understanding of beam ion's confinement property and beam-ion-driven magnetohydrodynamic (MHD) instabilities in TT-1.
書誌情報 Fusion Engineering and Design

巻 188, 号 March 2023, p. 113419, 発行日 2023-01-07
出版者
出版者 Elsevier
ISSN
収録物識別子タイプ ISSN
収録物識別子 0920-3796
書誌レコードID
収録物識別子タイプ NCID
収録物識別子 AA11529170
DOI
関連タイプ isVersionOf
識別子タイプ DOI
関連識別子 https://doi.org/10.1016/j.fusengdes.2023.113419
権利
権利情報 © 2023 Elsevier B.V.
関連サイト
識別子タイプ DOI
関連識別子 https://doi.org/10.1016/j.fusengdes.2023.113419
関連名称 Publisher version
著者版フラグ
出版タイプ AM
出版タイプResource http://purl.org/coar/version/c_ab4af688f83e57aa
NAIS
13310
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