• Title/Summary/Keyword: Fusion power

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OVERVIEW OF SUPERCONDUCTING MAGNET POWER SUPPLY SYSTEM FOR THE KSTAR 1ST PLASMA EXPERIMENT

  • Choi, Jae-Hoon;Yang, Hyung-Lyeol;Ahn, Hyun-Sik;Jang, Gye-Yong;Lee, Dong-Keun;Kim, Kuk-Hee;Hahn, Sang-Hee;Kim, Chang-Hwan;Hong, Jae-Sic;Chu, Yong;Kong, Jong-Dae;Hong, Seong-Lok;Hwang, In-Sung
    • 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.

Superconducting Magnet Power Supply System for the KSTAR 2nd Plasma Experiment and Operation

  • Choi, Jae-Hoon;Lee, Dong-Keun;Kim, Chang-Hwan;Jin, Jong-Kook;Han, Sang-Hee;Kong, Jong-Dae;Hong, Seong-Lok;Kim, Yang-Su;Kwon, Myeun;Ahn, Hyun-Sik;Jang, Gye-Yong;Yun, Min-Seong;Seong, Dae-Kyung;Shin, Hyun-Seok
    • 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.

Estimation of fuel operating ranges of fusion power plants

  • Slavomir Entler ;Jan Horacek ;Ondrej Ficker ;Karel Kovarik ;Michal Kolovratnik ;Vaclav Dostal
    • Nuclear Engineering and Technology
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    • v.55 no.7
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    • pp.2687-2696
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    • 2023
  • The fuel operating ranges of fusion tokamak-based power plants are estimated using the improved engineering breakeven equation. The Lawson criterion equations are derived in the form of a triple product with a focus on engineering breakeven and the subbreakeven operating range. The relationship of fuel parameters to the power plant net efficiency is outlined. Analysis shows that the operating ranges of the suitable fuel parameters form a closed area, the size of which affects the net efficiency of the power plant. The obtained fuel operating ranges confirm the well-known fact that DT fuel is currently the only fusion fuel useable in tokamak-based fusion power plants. It is also shown that the energy utilization of pB fuel is possible in the subbreakeven operating range but is conditioned by the very high efficiency of the power plant equipment. For the utilization of DD, DHe3, and pB fuels, the required magnetic fields are indicatively estimated.

High Power ICRF Experiments in the Large Helical Device

  • Kasahara, H.;Saito, K.;Seki, T.;Kumazawa, R.;Kubo, S.;Shimozuma, T.;Yoshimura, Y.;Igami, H.;Takahashi, Y.;Nakamura, Y.;Shimpo, F.;Nomura, G.;Takahashi, C.;Yokota, M.;Mutoh, T.
    • Proceedings of the Korean Vacuum Society Conference
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    • 2007.08a
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    • pp.179-179
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    • 2007
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Controls on KSTAR Superconducting Poloidal Field (PF) Magnets

  • Hahn, Sang-Hee;Kim, K.H.;Choi, J.H.;Ahn, H.S.;Lee, D.K.;Park, K.R.;Eidietis, N.W.;Leuer, J.A.;Walker, M.L.;Yang, H.L.;Kim, W.C.;Oh, Y.K.
    • Progress in Superconductivity and Cryogenics
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    • v.10 no.4
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    • pp.23-28
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    • 2008
  • As a part of the plasma control system (PCS) for the first plasma campaign of KSTAR, seven sets of fast feedback control loop for the superconducting poloidal field magnet power supply (PF MPS) have been implemented. A special real-time digital communication interface has been developed for the simultaneous exchanges of the current/voltage data from the 7 sets of 12-thyristor power supplies in a 200 microsecond control cycle. Preliminary power supply tests have been performed before actual cooldown of the device. A $29mH/50m{\Omega}$ solenoid dummy has been fabricated for a series of single power supply tests. Connectivity and response speed of the plasma control system have been verified. By changing hardware cabling, this load was also used to estimate mutual inductance coupling effects of two geometrically adjacent solenoid coils on each power supply. After the cooldown was complete, each pair of the up/down symmetric PF coils has been serially connected and tested as part of the device commissioning process. Bipolar operation and longer pulse attempts have been investigated. The responses of the coils and power supplies corresponding to the plasma magnetic controls in plasma discharges are also analyzed for the future upgrades.

EMC/LVD Compatibility Evaluation of ITER AC/DC Converter Subrack by EN 61000 and IEC 61010 (ITER AC/DC Converter 서브랙의 EN 61000 및 IEC 61010에 의한 EMC/LVD 시험평가)

  • Shin, Hyun-Kook;Oh, Jong-Seok;Song, In-Ho;Suh, Jae-Hak;Choi, Jung-Wan
    • The Transactions of the Korean Institute of Power Electronics
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    • v.26 no.3
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    • pp.222-226
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    • 2021
  • To comply with CE marking requirements, the electromagnetic compatibility (EMC) and low-voltage directive (LVD) tests are conducted on the sub-racks of International Thermonuclear Experimental Reactor (ITER) AC/DC converters and bypass switches. The EMC tests consist of a series of tests, including the electromagnetic interference test, the electromagnetic field immunity test, and the rapid transient burst immunity test. In the LVD test, the electric shock protection test, the xcessive temperature limit and heat resistance of equipment tests, and the fire spread prevention test are performed. This work presents and reviews the European Directive for EMC/LVD and introduces the methods of EMC and LVD tests for the sub-racks of AC/DC converters and bypass switches. It also evaluates the test method and results to meet the European Directive requirements for CE marking. The sub-racks of ITER AC/DC converters and bypass switches successfully pass the EMC and LVD tests.

Arc Fusion Protection of Covered Conductors Using AFPD (섬락 단선 방지 장치에 의한 피복 절연 가공배전 선로의 유도뢰애 의한 단선 방지)

  • Lee, Yong-Han;Jung, Dong-Hak;Ha, Bok-Nam;NamKung, Do;Kim, Myong-Soo
    • Proceedings of the KIEE Conference
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    • 1997.07c
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    • pp.800-802
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    • 1997
  • After flashover occurs on the overhead distribution line by lighting strokes(direct or induced), the power frequency arc current continues. If lightning flashover occurs on the overhead lines using covered conductors, the power frequency art current with fixed path overheats the conductor, and arc fusion fault can be occurred. There are two categories protecting or reducing methods of arc fusion faults caused by lightning stokes. - Reducing lightning flashover rate : G/W, LA, etc. - Protection by AFPD(Arc Fusion Protection Device) : power follow current interruption. This paper presents lightning surge phenomena on overhead distribution lines and protecting performance of arc fusion Protection devices to the lightning strokes nearby overhead line.

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Investigation on the thermal butt fusion performance of the buried high density polyethylene piping in nuclear power plant

  • Kim, Jong-Sung;Oh, Young-Jin;Choi, Sun-Woong;Jang, Changheui
    • Nuclear Engineering and Technology
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    • v.51 no.4
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    • pp.1142-1153
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    • 2019
  • This paper presents the effect of fusion procedure on the fusion performance of the thermal butt fusion in the safety class III buried HDPE piping per various tests performed, including high speed tensile impact, free bend, blunt notched tensile, notched creep, and PENT tests. The suitability of fusion joints and qualification procedures was evaluated by comparing test results from the base material and buttfusion joints. From the notched tensile test result, it was found that the fused joints have much lower toughness than the base material. It was also identified that the notched tensile test is more desirable than the high speed tensile impact and free bend tests presented in the ASME Code Case N-755-3 as a fusion qualification test method. In addition, with regard to the single low-pressure fusion joint performances, the procedure given by the ISO 21307 was determined to be better that the one specified in the Code Case N-755-3.

Target alignment method of inertial confinement fusion facility based on position estimation

  • Lin, Weiheng;Zhu, Jianqiang;Liu, Zhigang;Pang, Xiangyang;Zhou, Yang;Cui, Wenhui;Dong, Ziming
    • Nuclear Engineering and Technology
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    • v.54 no.10
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    • pp.3703-3716
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    • 2022
  • Target alignment technology is one of the most critical technologies in laser fusion experiments and is an important technology related to the success of laser fusion experiments. In this study, by combining the open-loop and closed-loop errors of the target alignment, the Kalman state observer is used to estimate the position of the target, which improves the observation precision of the target alignment. Then the optimized result is used to guide the alignment of the target. This method can greatly optimize the target alignment error and reduce uncertainty. With the improvement of the target alignment precision, it will greatly improve the reliability and repeatability of the experiments' results, thereby improving the success rate of the experiments.