• 한국진공학회:학술대회논문집
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• 한국진공학회 2011년도 제40회 동계학술대회 초록집
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• pp.218-218
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• 2011

Tokamak 플라즈마는 ICRF 영역에서 외곽 플라즈마 부근에 CUT-OFF밀도가 있으며, 이보다 낮은 밀도에서는 ICRF 전파가 투과하지 못하는 전파 장벽이 존재하게 된다. 이때 전달되는 효율은 안테나 부하저항으로 알 수 있으며, 이는 전파장벽이 낮을수록 큰 값을 갖는다. 따라서, 전파장벽은 에너지 전달 효율을 급격히 떨어뜨리므로 전파 장벽의 특성을 분석하고 이를 낮추는게 매우 중요하다. CUT-OFF 밀도는 자기장, k_par, 구동주파수, 플라즈마 밀도에 의존하게 되고, 측정한 밀도 분포를 통해 전파장벽의 구간을 안다면,이를 이용하여 안테나의 부하저항과의 의존성을 알 수 있다. 본 연구에서는 이러한 외곽 플라즈마 밀도 분포를 얻기 위해 토카막의 언저리 영역에서 플라즈마에 간섭없이 $10^{18}{\sim}10^{19}m^{-3}$의 플라즈마 밀도를 진단할 수 있는 9GHz~30GHz의 microwave를 사용하는 반사계를 설계하였으며,플라즈마 변수와 ICRF 운전 변수에 따른 부하저항의 계산결과와 반사계 시스템 설계에 대한 내용이 발표될 것이다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(4)
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• pp.443-448
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• 1996

In this paper, the 100 % non-inductive current drive scenarios are addressed for the steady-state operation on KT-2 tokamak, with the profile control using fast wave and lower hybrid wave as the external tools. Considering the stability, the well-aligned current profiles with a reversed-shear and $q_{min}$ > 2.0 has been favor-able in high ${\beta}_{p}$ plasma, together with a possibly higher bootstrap current fraction. Therefore, the effects of the auxiliary heating power profile on the control of MHD favorable current profile are evaluated in detail.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2000년도 하계학술대회 논문집 B
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• pp.801-803
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• 2000

The large scale magnets like thermalnuclear fusion devices are necessary for superconducting CICC cable, When the Cable In Conduit Conductors(CICC) is occurred by the external turbulence, the CICC occurs to quench, The CICC can be broken because the CICC spends all energy in the quench-happened spot. Therefore, it is necessary to develop measurement systems of the quench detection. The measurement systems of the relative good degree of efficiency are the voltage tap sensors. The weak points of voltage tap sensors are effected by EMF noise and inductance. The thermalnuclear fusion devices easily can't measure inductance value because of plasma current. In the experiment, The value of inductance was estimated by FEM techniques and the decrement of Inductance value measured as long as remaining plasma current.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1999년도 하계학술대회 논문집 A
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• pp.256-258
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• 1999

The quench characteristics of cable consisted of superconducting strand for Tokamak system are observed and analyzed. The superconducting strands chrome-plated are twisted into cable. This cable was wound on bobbin and quench test is carried out by pulse source. At about 2500A the cable quenched.

• Nuclear Engineering and Technology
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• 제41권6호
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• pp.807-812
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• 2009

An ICRF discharge cleaning and a fast wave electron heating experiment were performed. For automated operation and providing the diagnostics of the ICRF system, the ICRF local network was designed and implemented. This internal network provides monitoring, RF protection, remote control, and RF diagnostics. All the functions of the control system were realized by customized DSP units. The DSP units were tied by a local network in parallel. Owing to the distributed feature of the control system, the ICRF local control system is quite flexible to maintain. Developing the subsystem is a more effective approach compared to developing a large controller that governs the entire system. During the first experimental campaign of the KSTAR tokamak, the control system operated as expected without any major problems that would affect the tokamak operation. The transmitter was protected from harmful over-voltage events through reliable operation of the system.

• 전력전자학회논문지
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• 제27권5호
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• pp.397-401
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• 2022

The construction of the ITER tokamak machine is ongoing at a 77% process rate to achieve the first plasma in 2025. The 18 sets of power supply systems comprising 400 MVA thyristor AC/DC converters for the superconducting magnets supplied by Korea (KO) are being installed with other systems, such as PF converters (China), DC busbars (Russia), and cooling water systems (India), in two buildings (Europe). The system interfaces have been defined during the design stage, and the systems have been manufactured. However, during the on-site installation work, several installation and integration issues emerged due to the manufacturing tolerance and design mistakes. To continue the installation and testing, the engineers of each system resolved the interface issues, planned the commissioning, and integrated the test plan. This paper describes the on-site installation status and issues and the commissioning plan of KO AC/DC converters.

• Nuclear Engineering and Technology
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• 제55권7호
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• pp.2687-2696
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• 2023

The fuel operating ranges of fusion tokamak-based power plants are estimated using the improved engineering breakeven equation. The Lawson criterion equations are derived in the form of a triple product with a focus on engineering breakeven and the subbreakeven operating range. The relationship of fuel parameters to the power plant net efficiency is outlined. Analysis shows that the operating ranges of the suitable fuel parameters form a closed area, the size of which affects the net efficiency of the power plant. The obtained fuel operating ranges confirm the well-known fact that DT fuel is currently the only fusion fuel useable in tokamak-based fusion power plants. It is also shown that the energy utilization of pB fuel is possible in the subbreakeven operating range but is conditioned by the very high efficiency of the power plant equipment. For the utilization of DD, DHe3, and pB fuels, the required magnetic fields are indicatively estimated.

• 핵융합뉴스레터
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• 통권42호
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• pp.18-19
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• 2009

국가핵융합연구소는 녹색 에너지로 기대되는 핵융합 에너지의 개발을 위해 선진 7개국이 공동으로 추진하고 있는 국제핵융합실험로(ITER)의 성공적인 운전에 관련된 현안 사안을 다루는 ITPA(International Tokamak Physics Activity) 전문가 회의를 지난 4월 21일부터 24일까지 4일간 국가핵융합연구소 회의실에서 개최하였다.

• 한국자기학회:학술대회 개요집
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• 한국자기학회 2007년도 동계학술연구발표회 및 스핀트로닉스와 나노물리에관한 국제심포지움
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• pp.246-247
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• 2007

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.1106-1107
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• 2005