• 한국초전도저온공학회:학술대회논문집
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• 한국초전도저온공학회 2003년도 추계학술대회 논문집
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• pp.307-310
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• 2003

The KSTAR (Korea Superconducting Tokamak Advanced Research) prototype TF (Toroidal Field) coil was tested in the superconducting coil test facility in KBSI (Korea basic Science Institute). The test was divided into several campaigns according to the objectives. The objectives of the first campaign were to cool the coil into operating temperature and to find any defect in the coil such as cold leaks. From the results of the first campaign, which was carried out during Jan. 2003, any defect in the TF prototype coil was not found. At the second campaign, the large-current charging experiment was one of the major issues, and was carried out during Aug. 2003 In this paper, the test preparation, and the test results of the second campaign were presented.

• Nuclear Engineering and Technology
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• 제38권8호
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• pp.785-792
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• 2006

The microwave heating system of KSTAR consists of ECH and LHCD. ECH and LHCD offer the benefits ofa reliable operation at the start of plasma formation and a non-inductive current drive durable steady state operation, respectively. LHCD uses a C-band microwave system with a frequency of 5 GHz. A pulsed power modulator with a power of 3.6 MW, $4{\mu}S$, 200 pps is required to drive the high-powered magnetron. The development of a pulse modulator with 1:4 pulse transformers is the focus of the research in this study. The peak power handling capability is 3.6 MW (45 kV, 90 A at load side with a pulse width of $4{\mu}S$). This paper describes the system overview and test results of the pulsed modulator. In particular, a simulated waveform is compared with the tested waveform.

• 센서학회지
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• 제25권1호
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• pp.8-12
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• 2016

A planar, light-weight, and low-cost notch filter structure is required for the KSTAR ECEI (Electron Cyclotron Emission Imaging) system to protect the mixer arrays from spurious plasma heating power. Without protection, this heating power can significantly degrade or damage the performance of the mixer array. To protect mixer arrays, a frequency selective surface (FSS) structure is the suitable choice as a notch filter to reject the spurious heating power. The FSS notch filter should be located between the lenses of the ECEI system. This paper presents a 170 GHz FSS notch filter for the KSTAR ECEI sensor application. The design of such an FSS notch filter is based on the single-sided square loop geometry, because that makes it relatively insensitive to the incident angle of incoming wave. The FSS notch filter exhibits high notch rejection with low pass-band insertion loss over a wide range of incident angles. This paper also reviews the simulated and measured results. The proposed FSS notch filter might be implemented in other millimeter-wave plasma devices.

• 전력전자학회:학술대회논문집
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• 전력전자학회 2015년도 전력전자학술대회 논문집
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• pp.467-468
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• 2015

능동형필터는 주로 비선형 부하로 부터 발생되는 정수배의 고조파를 보상하는데 응용되어 왔다. 본 논문에서는 국가핵융합연구소(NFRI)의 KSTAR 주장치의 전원공급장치인 PF MPS가 가동되면서 특이한 저차수 대역의 비정수 고조파가 발생되는데 이는 MG(motor generator)와 RPC (Reactive Power Compensator)간의 병렬공진 확대현상으로 나타나 고조파 전류의 증가, 전압왜형 상승 등 안정적인 전력계통 운영에 영향을 주고 있다. 따라서 이의 원인이 되는 특이성의 비정수 고조파를 저감시키기 위한 제어 알고리즘 개발과 모의시험에 관한 연구내용을 다루고자한다. 지금까지 개발된 알고리즘은 주로 정수배 고조파만을 대상으로 한 FFT의 일괄보상, 혹은 개별차수 보상방식이었으나 여기서는 DQ 변환 알고리즘을 채용하여 정수배 고조파는 물론 0.5차 단위의 비정수 고조파까지 제어하는 기술을 다루었다.

• 한국진공학회:학술대회논문집
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• 한국진공학회 2009년도 제38회 동계학술대회 초록집
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• pp.296-296
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• 2010

핵융합로에서 플라즈마 대항부품(Plasma facing components) 내부에 흡착되는 수소에 대한 조절은 삼중수소의 흡착으로 인한 운전시간 제한뿐만 아니라 원활한 토카막 방전유지를 위하여 매우 중요한 문제이다. 특히 고주파 가열에서는 수소를 소수종으로 사용하는 경우 수소 농도에 대한 수 % 이내의 정밀한 조절이 필요하므로 플라즈마 대항부품 내부의 수소 함유량에 대한 조절이 매우 중요하다. 2009 KSTAR 실험에서는 인보드와 아웃보드에 흑연재질의 플라즈마 대항부품을 사용하였다. 이들은 설치후 진공배기 이전까지 장시간 공기에 노출되었으므로 상당량의 수소와 물이 흡착되었으리라고 예상되었다. 본 발표에서는 잔류가스분석기 및 분광법을 이용하여 토카막 방전중의 수소와 중수소의 비율을 측정하였고 이들을 토카막 방전유지시간, 방전세정과정 등을 매개변수로 분석하였다. 한달여의 토카막 실험을 통하여 플라즈마 대항부품에 대한 활발한 세정활동이 이루어졌음에도 불구하고 중수소에 대한 수소의 농도는 50 % 근방의 값을 유지하였다. 2010년도 실험에서는 신규 설치되는 디버터도 흑연을 사용할 계획이므로 플라즈마 대항부품의 수소흡착량은 더욱 증가할 것이다. 따라서 2010년도에 KSTAR 플라즈마에서 효과적인 고주파 가열을 달성하기 위하여는 강력한 세정 활동을 포함한 수소의 농도 제거활동이 선행되어야한다.

• Nuclear Engineering and Technology
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• 제55권1호
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• pp.100-108
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• 2023

In this study, a neural network model inspired by a one-dimensional convolution U-net is developed to automatically accelerate edge localized mode (ELM) detection from big diagnostic data of fusion devices and increase the detection accuracy regardless of the hyperparameter setting. This model recognizes the input signal patterns and overcomes the problems of existing detection algorithms, such as the prominence algorithm and those of differential methods with high sensitivity for the threshold and signal intensity. To train the model, 10 sets of discharge radiation data from the KSTAR are used and sliced into 11091 inputs of length 12 ms, of which 20% are used for validation. According to the receiver operating characteristic curves, our model shows a positive prediction rate and a true prediction rate of approximately 90% each, which is comparable to the best detection performance afforded by other algorithms using their optimized hyperparameters. The accurate and automatic ELM-burst detection methodology used in our model can be beneficial for determining plasma properties, such as the ELM frequency from big data measured in multiple experiments using machines from the KSTAR device and ITER. Additionally, it is applicable to feature detection in the time-series data of other engineering fields.

• 한국진공학회:학술대회논문집
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• 한국진공학회 2011년도 제40회 동계학술대회 초록집
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• pp.240-240
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• 2011

The first neutral beam injector (NBI-1) has been developed for the Korea Superconducting Tokamak Advanced Research (KSTAR) tokamak. A first long pulse ion source (LPIS-1) has been installed on the NBI-1 for an auxiliary heating and current drive of KSTAR core plasmas. Performance of ion and neutral beam extractions in the LPIS-1 was investigated initially on the KSTAR NBI-1 system, prior to the neutral beam injection into the main plasmas. The ion source consists of a JAEA magnetic bucket plasma generator with multi-pole cusp fields and a set of KAERI prototype-III tetrode accelerators with circular apertures. The inner volume of plasma generator and accelerator column in the LPIS-1 is approximately 123 liters. Final design requirements for the ion source were a 120 kV/ 65 A deuterium beam and a 300 s pulse length. The extraction of ion beams was initiated by the formation of arc plasmas in the LPIS-1, called as an arc-beam extraction method. A stable ion beam extraction of LPIS-1 has been achieved up to an 100 kV/42 A for a 4 s pulse length and an 80 kV/25 A for a 14 s pulse length. Optimum beam perveance of 1.21 microperv has been found at an accelerating voltage of 80 kV. Neutralization efficiency has been measured by using a water flow calorimetry (WFC) method of calorimeter and an operation of bending magnet. The full-energy species of ion beams have been detected by using the diagnostic method of optical multichannel analyzer (OMA). An arc efficiency of the LPIS was 0.6~1.1 A/kW depending on the operating conditions of arc discharge.

• 과학과기술
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• 통권511호
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• pp.45-49
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• 2011

• 한국진공학회:학술대회논문집
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• 한국진공학회 1998년도 제16회 학술발표회 논문개요집
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• pp.150-150
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• 1998

• 한국진공학회:학술대회논문집
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• 한국진공학회 1998년도 제16회 학술발표회 논문개요집
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• pp.152-152
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• 1998