• Progress in Superconductivity
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• v.8 no.2
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• pp.193-201
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• 2007

Since the margins for the minimum quench energy and for the operating current in the superconducting magnet determine the operating regime of the magnet, a thermal stability analysis for the KSTAR superconducting magnet system is performed using 1-D Gandalf code. The result shows that the minimum quench energy is about 500 mJ/cc and the operating current margin is about 70 %. These values are larger than those of the KSTAR design criteria and the KSTAR superconducting magnet system can be operated stably under various experimental environments.

• Nuclear Engineering and Technology
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• v.38 no.8
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• pp.793-802
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• 2006

The design concept of a bending magnet to be installed in the KSTAR NBI system is presented. It is the function of a bending magnet that removes unconverted ions from the main beam stream and produces an 8 MW, 120 keV deuterium neutral beam. In order to determine the proper size and shape of the bending magnet, a parametric study on the B-field pattern was carried out by changing the dimensions of the pole face model. In addition, the detailed trajectories of the dominant ion species produced in the beam line were calculated. The electrical and cooling parameters of the coil assembly were also estimated.

• Proceedings of the KIEE Conference
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• 2003.04a
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• pp.355-358
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• 2003

본 연구에서는 차세대 초전도 핵융합장치(KSTAR)의 가열장치인 중성입자입사장치(NBI : Neutral Beam Injection) 시스템 중 휨 전자석(Bending magnet)의 중요한 파라메타인 전류에 따른 온도상승값과 B-field의 측정을 행하고 그 결과를 나타내었다. 휨 전자석(Bending magnet)은 중성입자입사장치(NBI) 시스템 중 중성화장치(Neutralizer) 후단에 설치되어, 미처 중성화되지 못한 이온들의 케도를 변경시켜 중성입자와 분리되도록 한 후 이온덤프에서 이들 이온들의 에너지가 흡수될 수 있도록 하는 역할을 한다. 사용전원은 15[V], 1200[A]의 가변전원을 사용하였고 전류값 변화에따른 온도상승값은 thermo couple 신호선을 이용하여 측정하였으며, B-field는 3차원 Gaussmeter를 이용하여 측정을 행하였다. 측정된 결과들은 설계시의 값과 비교분석을 행하여 오차를 줄여나가고자 하였고 향후 NBI 주 진공용기에 장착하여 중성입자입사장치의 개발 수행을 행하게 될 것이다.

• Nuclear Engineering and Technology
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• v.40 no.6
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• pp.459-466
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• 2008

The KSTAR Magnet Power Supply (MPS) was dedicated to the SC coil commissioning and $1^{st}$ plasma experiment as a part of the system commissioning. Although many efforts to develop large-current power supplies that are useful for high power electronic devices have been made in various application fields, such as for large metal-plating devices, there were clear discrepancies between conventional power supply technologies and that for the SC coils due to the special SC coil load conditions. Therefore, most of the power supply technologies for the SC coils were a challenge in the domestic research area due to their limited application. However, the MPS commissioning result showed that all of the hardware and controlling software operated well, and this result finally led to the success of SC coil commissioning and the KSTAR $1^{st}$ plasma experiment. This paper will describe key features of KSTAR MPS for the $1^{st}$ plasma experiment, and will also report the commissioning results of the magnet power supplies.

• Journal of Electrical Engineering and Technology
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• v.8 no.2
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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.

• Proceedings of the SAREK Conference
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• 2008.11a
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• pp.413-418
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• 2008

The toroidal field magnet power supply (TF MPS) for the KSTAR was constructed in August, 2007 and started the operation for the commissioning in March, 2008. The main role of the TF MPS is to supply the electric power to the TF magnet of the KSTAR. The water cooling components of the TF MPS are 16 stacks, busbar of 70 meters. For the cooling of the TF MPS, the D I water cooling system was designed and installed. The water cooling system consists of several pumps, heat exchangers, D I water polishing system and so on. The water cooling system for the TF MPS was tested under the 15 kA current charging condition. In this paper be discussed about the system performance and other parameters.

• Proceedings of the Korean Nuclear Society Conference
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• 2005.05a
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• pp.1092-1093
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• 2005

• Nuclear Engineering and Technology
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• v.40 no.6
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• pp.467-476
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• 2008

To keep the superconducting (SC) magnet coils of KSTAR at proper operating conditions, not only the coils but also other cold components, such as thermal shields (TS), magnet structures, SC bus-lines (BL), and current leads (CL) must be maintained at their respective cryogenic temperatures. A helium refrigeration system (RRS) with an exergetic equivalent cooling power of 9 kW at 4.5 K without liquid nitrogen ($LN_2$) pre-cooling has been manufactured and installed. The main components of the KST AR helium refrigeration system (HRS) can be classified into the warm compression system (WCS) and the cryogenic devices according to the operating temperature levels. The process helium is compressed from 1 bar to 22 bar passing through the WCS and is supplied to cryogenic devices. The main components of cryogenic devices are consist of cold box (C/B) and distribution box (D/B). The C/B cool-down and make the various cryogenic helium for the KSTAR Tokamak and the various cryogenic helium is distributed by the D/B as per the KSTAR requirement. In this proceeding, we will present the commissioning results of the KSTAR HRS. Circuits which can simulate the thermal loads and pressure drops corresponding to the cooling channels of each cold component of KSTAR have been integrated into the helium distribution system of the HRS. Using those circuits, the performance and the capability of the HRS, to fulfill the mission of establishing the appropriate operating condition for the KSTAR SC magnet coils, have been successfully demonstrated.

• 핵융합뉴스레터
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• s.46
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• pp.28-28
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• 2010

• Journal of the Korean Vacuum Society
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• v.16 no.5
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• pp.388-396
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• 2007

KSTAR (Korea Superconducting Tokamak Advanced Research) current lead system (CLS) has a role to interconnect magnet power supply (MPS) in room temperature (300 K) and superconducting (SC) bus-line, electrically. For the first plasma experiments, it should be assembled 4 current leads (CL) on toroidal field (TF) current lead box (CLB) and 14 leads on poloidal field (PF) CLB. Two current leads, with the design currents 17.5 kA, and SC bus-lines are connected in parallel to supply 35 kA DC currents on TF magnet. Whereas, it could supply $20\;{\sim}\;26\;kA$ to each pairs of PF magnets during more than 350 s. At the cold terminals of the leads, there are joined SC bus-lines and it was constructed helium coolant control system, aside from main tokamak system, to protect heat flux through current leads and enhanced Joule heat due to supplied currents. Throughout the establishment processes, it was tested the high vacuum pumping, helium leak of the helium lines and hardwares mounted between the helium lines, flow controls for CL, and liquid nitrogen cool-down of possible parts (current leads, CL helium lines, and thermal shield helium lines for CLB), for the accomplishment of the required performances.