Current status of the KSTAR construction

Bak, J.S.; Yang, H.L.; Oh, Y.K.; Park, Y.M.; Park, K.R.; Choi, Changho; Kim, W.C.; Sa, J.W.; Kim, H.K.; Lee, G.S.

doi:10.1016/j.cryogenics.2007.04.022

Cited by 6 publications

(4 citation statements)

References 2 publications

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“…Superconducting magnets are designed to confine deuterium-tritium plasma in the current and planned fusion devices [2]- [4]. The magnet coils were wound using cable-in-conduit superconducting conductor.…”

Section: Introductionmentioning

confidence: 99%

Testing of the Ceramic Insulation Break for Fusion Device

Liu

Pan

et al. 2014

IEEE Trans. Appl. Supercond.

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Large magnet system is an essential component of most current or planned fusion devices. Axial insulation breaks are required in order to electrically isolate the cryogenic distribution system from the potential high voltage of the magnet system and bus bars. The epoxy resin based insulation break could be the weak link in magnet design, due to insulation sensitivity to high irradiation doses. The Al 2 O 3 ceramic material instead of epoxy based material was used to manufacture the insulation break. Kovar alloy which has a similar mean coefficient of thermal expansion with Al 2 O 3 ceramic in the temperature range of 300-1073 K was used as two ends of the insulation breaks. The ceramic tubes and Kovar alloy tubes were vacuum brazed together using silver-based filler at 1073 K. The helium tightness, the insulation resistances and dielectric breakdown were checked at room temperature and LN 2 temperature. Then 2 kN traction and compression were tested at room temperature and LN 2 temperature. The maximum tensile force of 8.62 kN and 8.18 kN were measured at room temperature and LN 2 temperature, respectively. The three point bending test was carried out. The test results of 4.5 kN and 3.6 kN were measured at room temperature and LN 2 temperature, respectively. The 50 thermal shock cycles were performed from 77 K to 300 K to ensure that the ceramic break could operate under rapid temperature change.

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Section: Introductionmentioning

confidence: 99%

Testing of the Ceramic Insulation Break for Fusion Device

Liu

Pan

et al. 2014

IEEE Trans. Appl. Supercond.

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“…The helical field lines can be generated by toroidal field (TF) magnet coils and poloidal field (PF) magnet coils . Through several decades' development, many fusion devices have been established, such as EAST, DIII‐D, NSTX, JET, Tore Supra, JT‐60SA, KSTAR . In order to resolve the issues of the design, construct and experiment of the fusion device, International Thermonuclear Experimental Reactor (ITER) is funded and run by seven member entities—the European Union (EU), China, the USA, Japan, Russia, India and South Korea.…”

Section: Introductionmentioning

confidence: 99%

Thermal hydraulic analysis of the HECLIC blanket breeder unit for CFETR

Lei

Song

2014

Int. J. Energy Res.

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SUMMARYChina Fusion Engineering Test Reactor (CFETR) is proposed by the China National Integration Design Group. A heliumcooled lithium ceramic (HECLIC) blanket for CFETR has been designed by Institute of Plasma Physics Chinese Academy of Sciences (ASIPP) and University of Science and Technology of China (USTC). The HECLIC blanket includes the tungsten armor, first wall (FW), breeder units (BUs), caps, stiffening grids and back plates. The BU consists of the beryllium pebble beds, lithium ceramic pebble beds and cooling plates. The stiffening grid reinforces the blanket structure and also cools the BU together with cooling plates. Thermal hydraulic analysis has been performed to assess the heat transfer coefficient (HTC) and temperature distribution. The results indicate that the velocity is fairly uniform in the cooling loops, and the HTC is high enough to remove the heat timely. The maximum temperatures are within the design temperature limits. Besides, optimization has been done to improve the layout of the cooling channels. In addition, thermal mechanical analysis has been carried out. The maximum stress can satisfy design limits, and it proves the feasibility of the design.

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“…These are divided in two parts in developing alternative energy which does not use fossil fuel not to produce CO2 and reducing energy consumption through efficiency improvement or loss reduction. Researches of renewable energy, such as wind and photovoltaic generation, connected and operated in grid and fusion plant which is in charge of supplying energy in the future are finally considered as the best way to solve the present energy problems [1,2]. However, renewable energy has a disadvantage of noncontrollability and nuclear fusion plants take a lot of time to put to practical use.…”

Section: Introductionmentioning

confidence: 99%

DC Electric Railway Loadflow Algorithm Considering Movement of Electric Vehicles

Lee¹

2012

Power and Energy Systems and Applications

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This paper is about loadflow algorithm considering movement of electric railway vehicle. The electric railway system is peculiar power system of which the location and power of vehicle are variable. Especially, as the variance of power induces huge fluctuation of catenary voltage as severe as the electric devices may be stressed, stabilization scheme is needed to be devised. To derive the accurate results, output data, location and power, from train performance simulator (TPS) are used. Calculating the rail potential, accuracy enhancement for railway vehicle voltage is attempted. Korean Seoul Metro Line 2 is selected for the test system and simulated to verify the substation voltage is often out of permissible voltage range. KEY WORDS DC electric railway system, Loadflow analysis, TPS

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Current status of the KSTAR construction

Cited by 6 publications

References 2 publications

Testing of the Ceramic Insulation Break for Fusion Device

Testing of the Ceramic Insulation Break for Fusion Device

Thermal hydraulic analysis of the HECLIC blanket breeder unit for CFETR

DC Electric Railway Loadflow Algorithm Considering Movement of Electric Vehicles

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