• Journal of Electrical Engineering and Technology
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• 제10권1호
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• pp.216-226
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• 2015

The neutral beam injection generate ultra-high temperature energy in the tokamak of nuclear fusion. The neutral beam injection make up arc power supply, filament power supply and acceleration & deceleration power supply. The arc power supply has characteristics of low voltage and high current. Arc power supply generate arc through constant output of voltage and current. So this paper proposed suitable buck converter for low voltage and high current. The proposed buck converter used parallel switch because it can be increased capacity and decrease conduction loss. When an arc generated, the neutral beam injection chamber occur high voltage. And it will break output capacitor of buck converter. Therefore the output capacitor was removed in the proposed converter. Thus the proposed converter should be designed for the characteristics of low voltage and high current. Also, the arc power supply should be guaranteed for system stability. The proposed parallel buck converter enables the system stability of the divided low output voltage and high current. The proposed converter with constant output be the most important design of the output inductor. In this paper, designed arc power supply verified operation of system and stability through simulation and prototype. After it is applied to the 288[kW] arc power supply for neutral beam injection.

• 한국진공학회:학술대회논문집
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• 한국진공학회 2016년도 제50회 동계 정기학술대회 초록집
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• pp.425.1-425.1
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• 2016

고온의 플라즈마를 긴 펄스 및 장시간 연속운전 유지기술 개발 및 연구를 위해서는 플라즈마는 더욱 가열되어야 하고, 고온 고밀도의 플즈마 상태를 유지시켜야 한다. 이러한 고성능 플라즈마 개발은 향후 핵융합 에너지의 상용화를 위한 절대필수적 기반기술이다. 현재 KSTAR 토카막에서는 플라즈마를 가열하기 위한 장치들 중 하나로서, 출력 6 MW 급의 중성입자빔을 입사하는 NBI (Neutral Beam Injection) 가열장치가 설치 운영 중에 있다. 이 NBI 가열장치는 진공환경에서 고온, 고압, 고전압 방전 및 수냉 등이 작동 및 운전되고 있기 때문에, 구성 부품 들의 미세한 구조적 결함에도 장치의 치명적 failed로 이어질 수 있다. 이번 연구에서는 NBI 가열장치의 특성상 극한 운전 환경에 있는 진공용기 부품 중 하나 인 빔인출을 위한 가속 그리드 (accelerating grid)의 구조적 손상및 결함 여부를 고속중성자 이미지 기법을 적용하여 내부를 투시 진단하였다. 가속 그리드는 copper로 제작되었고, 빔인출을 위한 원형의 구멍과 냉각관을 가진 평면판 형태로 되었다. 본 연구에서 내부투시 및 진단할 수 있는 고속중성자 이미징 기법의 적용으로 진공용기 부품 및 장치의 구조적 결함 및 손상 여부를 판단 가능하다는 연구 결과를 얻었다.

• 한국초전도ㆍ저온공학회논문지
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• 제19권4호
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• pp.31-39
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• 2017

European R&D on designing their version of a DEMO fusion tokamak has recently resulted in the testing of a prototype $Nb_3Sn$ Cable-in-Conduit Conductor (CICC) for the DEMO TF coil. The characteristics and reported results of low temperature performance tests with the prototype CICC sample are compared with those from CICC samples incorporating other recent $Nb_3Sn$ cable designs. The EU-DEMO TF CICC prototype shows performance characteristics similar to that of the ITER CS CICC with short twist pitch. This is a first for a CICC sample that does not have a circular cross section. Assessment of its internal magnetostatic self-field suggests that a reduction in the internal self-field due to the rectangular geometry of the EU-DEMO TF CICC prototype compared to one with a circular geometry may have contributed to the performance characteristics showing current sharing temperature ($T_{cs}$) initially increase then stabilize with repeated electromagnetic loading, similarly to ITER CS CICC results. However, constraints on the internal self-field are not a sufficient condition for this $T_{cs}$ characteristic to occur.

• 한국초전도저온공학회:학술대회논문집
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• 한국초전도저온공학회 2002년도 학술대회 논문집
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• pp.173-176
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• 2002

Fundamental failure mode in a laminated composite pinned joint is proposed to assess damage resulting from stress concentration in the plate. The joint area is a region with stress concentrations thus a complicated stress state exists. The modeling of damage in a laminated composite pinned joint presents many difficulties because of the complexity of the failure process. In this study, the effect on the bearing strength of the pin jointed Carbon Fiber Reinforced Plastics (CFRP) composites for magnet support structure of KSTAR tokamak with various parameters such as edge distance to diameter, width to diameter, and the temperature of $23^{\circ}C$, $-76^{\circ}C$, and $-196^{\circ}C$ was examined by comparing the experimental results with finite element analysis.

• 한국초전도ㆍ저온공학회논문지
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• 제5권1호
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• pp.71-75
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• 2003

The conduit fer superconducting cable is welded and plastically deformed during the jacketing process to make the CICC (Cable-in-Conduit-Conductors) fer a fusion magnet. The jacketing process of KSTAR (Korea Superconducting Tokamak Advanced Research) conductors is composed of several sequential steps such as rounding, welding, sizing, and square-rolling. Since the welded zone in Incoloy 908 conduit is brittle and easy to have flaws, there may be a possibility of stress corrosion cracking during the heat treatment of coil when both the induced tensile residual stress and the concentration of oxygen in the furnace are sufficiently high. The steps of the jacketing process were simulated using the finite element method of the commercial ABAQUS code, and the stress distribution in the conduit in each step was calculated, respectively. Furthermore, the variations of residual welding stresses through the steps of the jacketing process were calculated and analyzed to anticipate the possibility of the stress corrosion cracking in the conduit. The concentrated high tensile residual welding stresses along the welding bead decrease by the plastic deformation of the following sizing step. The distribution in residual stresses in the conductor for magnet coil is mainly governed by the last step of square-rolling.

• Journal of Mechanical Science and Technology
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• 제14권9호
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• pp.985-996
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• 2000

The issue of quench is related to safety operation of large-scale superconducting magnet system fabricated by cable-in-conduit conductor. A numerical method is presented to simulate the thermal hydraulic quench characteristics in the superconducting Tokamak magnet system, One-dimensional fluid dynamic equations for supercritical helium and the equation of heat conduction for the conduit are used to describe the thermal hydraulic characteristics in the cable-in-conduit conductor. The high heat transfer approximation between supercritical helium and superconducting strands is taken into account due to strong heating induced flow of supercritical helium. The fully implicit time integration of upwind scheme for finite volume method is utilized to discretize the equations on the staggered mesh. The scheme of a new adaptive mesh is proposed for the moving boundary problem and the time term is discretized by the-implicit scheme. It remarkably reduces the CPU time by local linearization of coefficient and the compressible storage of the large sparse matrix of discretized equations. The discretized equations are solved by the IMSL. The numerical implement is discussed in detail. The validation of this method is demonstrated by comparison of the numerical results with those of the SARUMAN and the QUENCHER and experimental measurements.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2009년도 제40회 하계학술대회
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• pp.101_102
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• 2009

KSTAR(Korea Superconducting Tokamak Advanced Reseach)장치는 차세대핵융합연구장치로써 30개의 초전도자석으로 구성된다. 이 초전도자석에 전원을 공급하게 되는 PF (Poloidal Field) MPS(Magnet Power Supply)는 12상 Pulse 운전을 하게 되는데 이때 $h=kp{\pm}1$의 특성고조파와 90%에 가까운 무효전력이 발생되어 KSTAR 전력계통과 인근 부하장치에 치명적인 영향을 줄 수 있어 고조파와 무효전력을 동시에 보상할 수 있는 최적의 무효전력보상장치의 도입은 필연적이다. 본 논문에서는 KSTAR 1st Plasma 실험시의 무효전력과 고조파를 저감하기 위해 설치했던 즉, 1단계 기계식 스위칭에 의한 RPC(Reactive power compensator)의 보상특성의 평가결과를 기반으로 KSTAR 2009년 Plasma 실험에 대비하여 이의 운전특성과 설치 공간에 따르는 제약 등을 고려하여 최적의 RPC 설계를 도출하기 위해 실시한 TSC(Thyristor Switch Capacitor)기반의 RPC[1] 모의해석 결과와 기술적 사항을 소개하고자 한다.

• 조명전기설비학회논문지
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• 제27권6호
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• pp.50-58
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• 2013

The Neutral Beam Injection(NBI) generates ultra-high temperature energy in the tokamak of nuclear fusion. The NBI consists of filament power supply acceleration and deceleration power supply and arc power supply(APS). The APS has characteristics of low voltage and high current. APS generate arc through constant output of voltage and current. So this paper proposed suitable buck converter for low voltage and high current. The case of proposed buck converter used parallel switch because it can increase capacity and decrease conduction loss. When an arc is generated, the NBI chamber occur high voltage. And it will break output capacitor of buck converter. Therefore the output capacitor was removed in the proposed converter. Thus buck converter with constant output is the most important design of the output inductor. In this paper, designed APS verified operation of system and stability through simulation and prototype.

• 한국초전도저온공학회:학술대회논문집
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• 한국초전도저온공학회 2001년도 학술대회 논문집
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• pp.41-44
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• 2001

Mechanical test of the Carbon Fiber Reinforced Plastics (CFRP) composite specimen was performed based on the ASTM code at the ambient and low temperature. Tension, compression in-plane shear, and inter-laminar shear properties of the composite laminates were evaluated experimentally using the Universal Testing Machine(UTM) system at the temperature of $24^{\circ}C$,$-76^{\circ}C$ , and $-196^{\circ}C$. From the test results it was found that the CFRP chosen for the Korea Superconducting Tokamak Advanced Research(KSTAR) magnet supporting post had smaller tensile strength and larger compressive strength at the low temperature than those of the ambient temperature because of material ductility.

• 한국진공학회지
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• 제7권4호
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• pp.285-292
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• 1998

KSTAR 토카막용 진공용기는 토러스형으로써 내부에 사람이 들어가 작업할 수 있 는 큰 종단면을 갖고 있다. 이 용기는 불순물이 적은 깨끗한 플라즈마 발생을 위해 기저압 력이 초고진공이어야 하며 각종 플라즈마 대향부품을 포함해서 용기전체를 $350^{\circ}C$까지 베이 킹하는 것으로 계획되어 있다. 진공용기의 형태가 삼차원적으로 복잡하고 토카막 가동중 용 기에 걸리는 다양한 임을 해소하기 위해 지지구조물이 설치되어 있으며 균일한 온도분포를 만들기 어려워서 베이킹시 큰 열응력이 발생할 것으로 예상된다. 이 논문에서는 진공용기의 불균일한 온도분포를 만들기 어려워서 베이킹시 큰 열응력이 발생할 것으로 예상된다. 이 논문에서는 진공용기의 불균일한 온도분포와 지지구조의 구속조건에 따라 열응력이 어떻게 변하는가를 살펴보고 가능한 해결책을 제시하려고 한다.