• 한국진공학회지
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• 제16권6호
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• pp.489-495
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• 2007

KSTAR 토카막은 현재 주장치 조립을 완료하고 "최초 플라즈마" 발생과 시운전을 준비하고 있다. 이를 위해 설치되어 있는 연료주입계는 배기 덕트 반대 쪽 한 곳만 주입구로 사용하기 때문에 균일하고 신속한 입자공급이 어렵다. 시운전이 끝나고 기본운전 단계가 되면 단순한 플라즈마 생성이 아니라 일정한 고밀도 토카막플라즈마 상태를 일정시간 고르게 유지해야 하므로 공간적으로 균일한 입자공급과 플라즈마 밀도 변화에 따른 신속한 제어가 가능한 연료공급계로 개선되어야 한다. 이런 개선점을 찾는 작업의 일환으로 우선 D-형 진공용기 및 플라즈마 컬럼을 사각단면 토러스로 묘사하는 모델을 만들고 연료공급 위치와 플라즈마의 전리율 및 배기확률에 따라 공간적인 입자분포가 어떻게 바뀌는지 몬테카를로 계산을 통해 분석했다.

• Journal of Electrical Engineering and Technology
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• 제8권2호
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• pp.326-330
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• 2013

The Korea Superconducting Tokamak Advanced Research (KSTAR) device is an advanced superconducting tokamak to establish scientific and technological bases for attractive fusion reactor. This device requires 3.5 Tesla of toroidal field (TF) for plasma confinement, and requires a strong poloidal flux swing to generate an inductive voltage to produce and sustain the tokamak plasma. KSTAR was originally designed to have 16 serially connected TF magnets for which the nominal current rating is 35.2 kA. KSTAR also has 7 pairs of poloidal field (PF) coils that are driven to 1 MA/sec for generation of the tokamak plasma according to the operation scenarios. The KSTAR Magnet Power Supply (MPS) was dedicated to the superconducting (SC) coil commissioning and $2^{nd}$ plasma experiment as a part of the system commissioning. This paper will describe key features of KSTAR MPS for the $2^{nd}$ plasma experiment, and will also report the engineering and commissioning results of the magnet power supplies.

• 센서학회지
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• 제25권1호
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• pp.46-50
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• 2016

During KSTAR plasma experiments, torsional $Alfv\acute{e}n$ waves in the frequency of few GHz or below were detected. To understand this plasma waves during the crash of MHD instabilities, an RF spectrometer has been developed for detection of the radiated RF signals in the KSTAR Tokamak. It has the capability of broadband RF spectral measurement (50 ~ 400 MHz). To detect the broadband RF signals which are radiated from the KSTAR systems, a broadband antenna is the key feature of the RF spectrometer. In this paper, a broadband bowtie antenna for detection of $Alfv\acute{e}n$-waves in the KSTAR Tokamak is presented. Planar-type bowtie antenna is designed and fabricated on an FR4 substrate with thickness of 1.6 mm. The antenna consists of bowtie shaped balanced radiators and broadband planar balun. The antenna is designed to have an input impedance of 50 Ohm, and a taper-shaped balun is adopted for field and impedance matching between 50 Ohm transmission line to 110 Ohm feeding network of balanced radiators. The implemented antenna provides around -3 to 3 dBi of gain for the whole frequency band. The VSWR of the bowtie antenna is less than 12:1 over the frequency bandwidth of 50 to 2000 MHz.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2003년도 추계학술대회
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• pp.1098-1102
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• 2003

Vacuum vessel of the KSTAR(Korea Superconducting Tokamak Advanced Research) tokamak is a fully welded structure with D-shaped cross-section. According to the requirements of the physics design, sixteen horizontal ports, sixteen slanted ports, sixteen baking and cooling ports, and twenty-four top and bottom vertical ports are designed for the diagnostics, plasma heating, vacuum pumping, and baking and cooling. Bellows on these ports are used for flexible components to absorb the relative displacement due to the vacuum vessel thermal expansion and the electromagnetic force between the vacuum vessel and the cryostat ports. Fatigue strength evaluation was performed to decide the dimension of the bellows. In order to assure the quality of the bellows, a prototype bellows for the neutral beam injection port has been fabricated and tested prior to main fabrication. It was conformed that the prototype bellows has sufficient fatigue strength and vacuum reliability in the expected load conditions.

• 한국진공학회:학술대회논문집
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• 한국진공학회 2010년도 제39회 하계학술대회 초록집
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• pp.314-314
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• 2010

For the optimal design of a tokamak-type reactor, self-consistent determination of a radial build of reactor systems is important and the radial build has to be determined by considering the plasma physics and engineering constraints which inter-relate various reactor systems. In a low aspect ratio (LAR) tokamak reactor with a superconducting toroidal field (TF) coil, the shield should provide sufficient protection for the superconducting TF coil and the shield plays a key role in determining the size of a reactor. To determine the radial build of a reactor, neutronic effects such as tritium breeding in the blanket, nuclear heating, and radiation damage to toroidal field (TF) coil has to be included in the systems analysis. In this work, the outboard blanket only is considered where tritium self-sufficiency is possible by using an inboard neutron reflector instead of breeding blanket. The reflecting shield should provide not only protection for the superconducting TF coil but also improved neutron economy for the tritium breeding in outboard blanket. Tungsten carbide, metal hydride such as titanium hydride and zirconium hydride can be used for improved shielding performance and thus smaller shield thickness. With the use of advanced technology in the shield, conceptual design of a compact superconducting LAR reactor with aspect ratio of less than 2 will be presented as a viable power plant.

• Nuclear Engineering and Technology
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• 제29권6호
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• pp.459-467
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• 1997

The steady-state behavior of recycling neutral atoms in a tokamak edge region has been analyzed through a two-dimensional Monte Carlo simulation. A particle tracking algorithm used in earlier research on the neutral particle transport is applied to this Monte Carlo simulation in order to perform more accurate calculations with the EDGETRAN code which was previously developed for a two-dimensional edge plasma transport in the authors' laboratory. The physical model of neutral recycling includes charge-exchange and ionization interactions between plasmas and neutral atoms. The reflection processes of incident particles on the device wall are described by empirical formulas. Calculations for density, energy, and velocity distributions of neutral deuterium-tritium atoms have been carried out for a medium-sized tokamak with a double-null configuration based on the KT-2 conceptual design. The input plasma parameters such as plasma density, ion and electron temperatures, and ion fluid velocity are provided from the EDGETRAN calculations. As a result of the present numerical analysis, it is noticed that a significant drop of the neutral atom density appears in the region of high plasma density and that the similar distribution of neutral energy to that of plasma ions is present as frequently reported in other studies. Relations between edge plasma conditions and the neutral recycling behavior are discussed from the numerical results obtained herein.

• 대한전기학회논문지:전기물성ㆍ응용부문C
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• 제54권3호
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• pp.120-126
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• 2005

The Korean Superconducting Tokamak Advanced Research (KSTAR) tokamak device is being constructed to perform long-pulse, high-beta, advanced tokamak fusion physics experiments. The long-pulse operation requires the non-inductive current drive system such as the Lower-Hybrid Current Drive (LHCD) system. The LHCD system drives the non-inductive plasma current by means of C-band RF with 2-MW CW power and 5-GHz frequency. For the LHCD test experiments, an RF test system is developed. It is composed of a 5-GHz, 1.5-MW pulsed magnetron and a compact pulse modulator with $4\;{\mu}s$ of pulse width. The pulse modulator provides the maximum output voltage of 45 kV and the maximum current of 90 A. It is composed of 7 stages of Pulse Forming Network (PFN), a thyratron tube (E2V, CX1191D), and a pulse transformer with 1:4 step-up ratio. In this paper, the detailed design and the performance test of the pulse modulator are presented.

• Nuclear Engineering and Technology
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• 제25권1호
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• pp.136-147
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• 1993

본 논문은 다음의 내용을 기술한다 : ⅰ) 토카막 플라즈마의 경계면을 정의하고 계산하는 폴로이달 자속의 수학적 모형을 플라즈마경계면과 등자속면이 일치한다는 사실로부터 수립한다. 따라서 플라즈마의 경계위치를 제어한다 함은 리미터 접선상의 여러 점들에서 자속값을 같게 만드는 것을 의미한다. ⅱ) 자속, 자장, 자장구배의 선형조합으로 최외각 폴로이달 등자속면을 측정하는 방법을 제시한다. 이 방법은 내부플라즈마변수를 알 필요가 없어서 폴로이달베타와 플라즈마전류분포의 변동에 따르는 수정이나 진공용기의 유도전류를 보상하지 않아도 된다. ⅲ) 플라즈마의 경계면 위치조정을 위한 궤환제어 알고리즘을 수립하고, PID 제어이론을 기초로 해당 전자장비를 제작한다. ⅳ) 본 플라즈마 제어계를 사용한 RTP토카막 실험의 결과를 논의한다.

• Nuclear Engineering and Technology
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• 제21권1호
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• pp.32-39
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• 1989

원형 단면을 가진 축대칭형 토카막 핵융합로에 적합할 수 있는 최적의 이상적 자기유체역학 베타값과 운전조건의 결정 방법을 제시하였다. 토로이달 전류밀도 분포로 조정되는 운전조건을 변화시키면서 이상적 자기유체역학 안정성을 유지시킬 수 있는 베타값의 한계를 계산하였다. 토로이달 전류밀도 분포에는 실험적 관찰들로부터 얻은 실험식들이 사용되었고, 베타 값의 한계를 결정하기 위해 필요로 여러 식들이 이 실험식들로부터 유도되었다. 토로이달 전류밀도의 각각 다른 분포에 대해서 다양한 베타 한계값 분포들이 얻어졌다. 이상적 자기 유체 역학 불안정성들에 의해 제안받는 최대의 베타값을 토카막의 기하학적 변수와 안전인자에 의한 scaling law로 표현하였다.

• 한국진공학회:학술대회논문집
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• 한국진공학회 2009년도 제38회 동계학술대회 초록집
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• pp.314-314
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• 2010

The design of the blanket and shield play a key role in determining the size of a reactor since it has an impact on the various reactor components. The blanket should produce enough tritium for tritium self-sufficiency and the shield should provide sufficient protection for the superconducting TF coil. Neutronic optimization of the blanket and the shield is necessary, and we coupled the system analysis with a neutronic calculation to account for the interrelation of the blanket and shield with the plasma performance of a reactor system in a self-consistent manner. By using the coupled system analysis code, the operational space for a low aspect ratio (LAR) tokamak reactor with a superconducting toroidal field (TF) coil is investigated with an spect ratio in the range of 1.5 - 2.5. The minimum major radius which satisfies all the physics and engineering requirements increases with the magnetic field at the magnetic axis. A required inboard shield thickness is mainly determined by the requirement on the protection of the TF coil against radiation damage. It is shown that to have a fusion power bigger than 3,000 MW in the LAR tokamak with a superconducting TF coil, a major radius bigger than 4.0 m is required.