Solenoid-free toroidal plasma start-up concepts utilizing only the outer poloidal field coils and a conducting centerpost바깥쪽 폴로이달 자기장 코일과 전도성 중심기둥을 사용한 솔레노이드 코일 없는 토로이달 플라즈마의 시작 시나리오

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An in-board ohmic solenoid, along with the shielding needed for its insulation, can dramatically increase the size and, hence, the cost of the future fusion power plant. In addition, an elimination of in-board ohmic solenoid greatly reduces the coil stresses and simplifies the coil design. In this thesis, two complementary solenoid-free plasma start-up approaches were examined: the one utilizes only the outer poloidal field (PF) coils to create a relatively high quality field null region while retaining significant poloidal flux and the another takes advantage of the poloidal flux stored in the conducting centerpost to create a start-up condition similar to that of the conventional ohmic solenoid method. For the first start-up scheme, dynamic modeling utilizing only outer PF coils were performed for the Next Step Spherical Torus (NSST) and the National Spherical Torus Experiment (NSTX) based on the static calculation results. Time-dependent calculations using the two-dimensional axisymmetric dynamic code and the plasma evolution code enabled to find the appropriate waveform of PF coils that satisfied various start-up conditions such as formation and sustainment of field null, a significant amount of magnetic flux for further plasma current ramp-up, force balance condition, sufficient size of the $E_tㆍB_t/B_{\perp} = 0.1kV/m$ contour for successful breakdown where $E_t$ is the toroidal electric field, $B_t$ is the toroidal magnetic field, and $B_{\perp}$ is the stray field perpendicular to the toroidal field. With the obtained PF coil current waveforms, it is shown that multipole quality field null can be sustained for several milli-seconds with a reasonably large size inside the vacuum vessel. The available induction fluxes at the expected starting time of the breakdown period are about 3.56Wb for the NSST and 0.15Wb for the NSTX, respectively. These flux values are expected to be sufficient to raise the plasma current up to a few mega-amperes and a few hundr...
Advisors
Choe, Won-Horesearcher최원호researcher
Description
한국과학기술원 : 물리학과,
Publisher
한국과학기술원
Issue Date
2005
Identifier
244472/325007  / 000995085
Language
eng
Description

학위논문(박사) - 한국과학기술원 : 물리학과, 2005.2, [ xi, 133 p. ]

Keywords

토카막 시작시나리오 솔레노이드 폴로이달 코일 중심기둥; Tokamak Start-up Solenoid-free PF-only Centerpost

URI
http://hdl.handle.net/10203/47351
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=244472&flag=dissertation
Appears in Collection
NE-Theses_Ph.D.(박사논문)
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