• Title/Summary/Keyword: fusion magnet

Search Result 61, Processing Time 0.028 seconds

Fault Analysis of AC/DC Converter for ITER Superconducting Magnet (ITER 초전도자석 전원공급장치의 고장해석)

  • Park, H.;Lee, S.;Jo, S.;Chung, I.;Hwang, K.;Liu, H.;Oh, J.S.;Choi, J.;Suh, J.H.
    • Proceedings of the KIPE Conference
    • /
    • 2012.11a
    • /
    • pp.243-244
    • /
    • 2012
  • ITER 초전도자석 전원공급장치에서 고장의 종류는 단락, 단락 외 컨버터 내부고장 그리고 여러 외부요인에 의한 고장 크게 세 가지로 구분된다. 여기서 단락 외 컨버터 내부고장과 외부요인에 의한 고장은 보호시스템 및 장치의 동작으로 인해 피해가 축소된다. 하지만 단락시에는 보호시스템이 동작하더라도 단락전류가 매우 커 큰 피해를 줄 수 있다. 또한 ITER 초전도자석 전원공급장치는 운전 중 발생 가능한 부하의 단락으로부터 초전도자석 및 다른 장치 등을 보호하기 위하여 ITER에서 요구하고 있는 FSC(Fault Suppression Capability: 고장 억제 능력) 조건을 만족해야 한다. FSC 조건에서 전원공급장치는 출력에서 300 kA의 단락전류가 흐를 경우에도 80 ms(50 Hz, 4주기)동안 전기적 고장 없이 견뎌야 한다. 본 논문에서는 전원공급장치에서 발생될 수 있는 주요 단락 항목을 소개하고, 최악의 조건에서 단락전류에 의한 전원공급장치의 고장해석을 통해 FSC 요건을 만족하는 소자 선정 및 구조설계의 적합성을 검증한다.

  • PDF

Preliminary Design of AC/DC Converters for ITER Superconducting Magnet (ITER 초전도자석 전원공급장치의 예비설계)

  • Choi, J.;Oh, J.S.;Suh, J.H.;Lee, S.;Jo, S.;Jung, W.;Park, H.;Chung, I.;Hwang, K.;Liu, H.
    • Proceedings of the KIPE Conference
    • /
    • 2012.11a
    • /
    • pp.245-246
    • /
    • 2012
  • ITER 초전도자석 전원공급장치의 예비설계가 실제 크기 6펄스 R&D 컨버터의 제작 및 시험결과를 기반으로 수행되었다. ITER 컨버터는 자체적으로 지지되는 알루미늄 버스바 구조로 제작되며, 이 버스바에 양면 클램핑 방식으로 조립되는 Thyristor 스위치는 4인치 규격으로써 컨버터의 종류에 따라 한 개의 암 당 8 - 16 개의 소자가 병렬로 구성된다. ITER 컨버터 예비설계는 알루미늄 버스바 구조설계, 컨버터 냉각설계, 컨버터 전기회로 설계, 컨버터 고장해석 및 보호설계, 시험절차 및 요건 등을 포함하며, 본 논문에서 그 설계결과를 기술한다. ITER 컨버터는 예비설계 결과를 기반으로 상세설계 및 제작설계를 거친 후 제작된다.

  • PDF

Preliminary Design of AC/DC Converter Control System for ITER Superconducting Magnet (ITER 초전도자석 전원공급장치 제어시스템의 예비설계)

  • Suh, J.H.;Oh, J.S.;Choi, J.;Hwang, K.C.;Kang, J.B.;Lee, W.S.;Seo, E.;Kim, H.G.;kim, M.K.
    • Proceedings of the KIPE Conference
    • /
    • 2012.11a
    • /
    • pp.251-252
    • /
    • 2012
  • ITER(국제핵융합실험로) 제어시스템은 중앙제어와 Plant System으로 구성되며 CODAC, Central Interlock, Central Safety System으로 구분된다. 초전도자석에 전류를 공급하는 AC/DC 컨버터 시스템은 2상한, 4상한 구조의 전원 장치, 초기 플라즈마 발생에 필요한 Switching Network Unit, 코일에 저장된 에너지의 급속 방전을 위한 Fast Discharge Unit 및 무효 전력 보상장치로 구성된다. 4상한 전원장치는 1, 2, 4, 6대의 전원 장치가 직렬 접속되어 무효전력 발생이 최소로 하도록 제어된다. 대용량의 무효전력이 급격히 변화는 환경에서 계통 전압을 유지하기위해 무효전력보상장치는 각 전원 장치가 예측한 무효전력 값을 이용하여 제어한다. 본 논문은 ITER 전원 장치를 운전하기 위한 제어시스템의 개요와 예비설계 결과이다.

  • PDF

Development of Hard-wired Instrumentation and Control for the Neutral Beam Test Facility at KAERI

  • Jung Ki-Sok;Yoon Byung-Joo;Yoon Jae-Sung;Seo Min-Seok
    • Journal of Electrical Engineering and Technology
    • /
    • v.1 no.3
    • /
    • pp.359-365
    • /
    • 2006
  • Since the start of the KSTAR (Korea Superconducting Tokamak Advanced Research) project, Instrumentation and Control (I&C) of the Neutral Beam Test Facility (NB-TF) has been striving to answer diverse requests arising from various facets during the project's development and construction phases. Hard-wired electrical circuits have been designed, tested, fabricated, and finally installed to the relevant parts of the system. In relation to the vacuum system I&C, controlling functions for the rotary pumps, a Roots pump, two turbomolecular pumps, and four cryosorption pumps have been constructed. I&C for the ion source operation are the temperature and flow rate signal monitoring, Langmuir probe signal measurements, gradient grid current measurements, and arc detector circuit. For the huge power system to be monitored or safely operated, many temperature measurement functions have also been implemented for the beam line components like the neutralizer, bending magnet, ion dump, and calorimeter. Nearly all of the control and probe signals between the NB test stand and the control room were made to be transmitted through the optical cables. Failures of coolant flow or beam line vacuum pressure were made to be safely blocked from influencing the system by an appropriate interlock circuit that will shut down the extraction voltage application to the system or prevent damages to the vacuum components. Preliminary estimation of the beam power through the calorimetric measurement shows that 87.9% of the total power of the 60kV/18A beam with 200 seconds duration is absorbed by the calorimeter surface. Most of these I&C results would be highly appropriate for the construction of the main NBI facility for the KSTAR national fusion research project.

Quench Protection System for the KSTAR Toroidal Field Superconducting Coil

  • Lee, Dong-Keun;Choi, Jae-Hoon;Jin, Jong-Kook;Hahn, Sang-Hee;Kim, Yaung-Soo;Ahn, Hyun-Sik;Jang, Gye-Yong;Yun, Min-Seong;Seong, Dae-Kyoung;Shin, Hyun-Seok
    • Journal of Electrical Engineering and Technology
    • /
    • v.7 no.2
    • /
    • pp.178-183
    • /
    • 2012
  • The design of the integrated quench protection (QP) system for the high current superconducting magnet (SCM) has been fabricated and tested for the toroidal field (TF) coil system of the Korea Superconducting Tokamak Advanced Research (KSTAR) device. The QP system is capable of protecting the TF SCM, which consists of 16 identical coils serially connected with a stored energy of 495 MJ at the design operation level at 35.2 kA per turn. Given that the power supply for the TF coils can only ramp up and maintain the coil current, the design of the QP system includes two features. The first is a basic fast discharge function to protect the TF SCM by a dump resistor circuit with a 7 s time constant in case of coil quench event. The second is a slow discharge function with a time constant of 360 s for a daily TF discharge or for a stop demand from the tokamak control system. The QP system has been successfully tested up to 40 kA with a short circuit and up to 34 kA with TF SCM in the second campaign of KSTAR. This paper describes the characteristics of the TF QP systems and test results of the plasma experiment of KSTAR in 2009.

Line Tracking Method of AGV using Sensor Fusion (센서융합을 이용한 AGV의 라인 트레킹 방법)

  • Jung, Kyung-Hoon;Kim, Jung-Min;Park, Jung-Je;Kim, Sung-Shin;Bae, Sun-Il
    • Journal of the Korean Institute of Intelligent Systems
    • /
    • v.20 no.1
    • /
    • pp.54-59
    • /
    • 2010
  • This paper present to study the guidance system as localization technique using sensor fusion and line tracking technique using virtual line for AGV(autonomous guided vehicle). An existing AGV could drive on decided line only. And representative guidance systems of such guidance system are magnet-gyro guidance and wired guidance. However, those have had the high cost of installation and maintenance, and the difficulty of system change according to variation of working environment. To solve such problems, we make the localization system which is fused with a laser navigation and gyro, encoder. The system is robust against noise, and flexible according to working environment through sensor fusion. For line tracking of laser navigation without wire guidance, we set the virtual line in program, and design the driving controller based on difference of angle and distance between AGV's position and decided virtual line. To experiment, we use the AGV which is made by ourselves, and experiment the line tracking repeatedly on same experimental environment. In result, maximum distance error between decided virtual line and AGV's position was less than 49.93mm, and we verified that the proposed system is efficient for line tracking of actual AGV.

Fuzzy and Proportional Controls for Driving Control of Forklift AGV (퍼지와 비례 제어를 이용한 지게차 AGV의 주행제어)

  • Kim, Jung-Min;Park, Jung-Je;Jeon, Tae-Ryong;Kim, Sung-Shin
    • Journal of the Korean Institute of Intelligent Systems
    • /
    • v.19 no.5
    • /
    • pp.699-705
    • /
    • 2009
  • This paper is represented to research of driving control for the forklift AGV. The related works that were studied about AGV as heavy equipment used two methods which are magnet-gyro and wire guidance for localization. However, they have weaknesses that are high cost, difficult maintenance according to change of environment. In this paper, we develop localization system through sensor fusion with laser navigation system and encoder, gyro for robustness. Also we design driving controller using fuzzy and proportional control. It considers distance and angle difference between forklift AGV and pallet for engaging work. To analyze performance of the proposed control system, we experiment in same working condition over 10 times. In the results, the average error was presented with 54.16mm between simulation of control navigation and real control navigation. Consequently, experimental result shows that the performance of proposed control system is effective.

Variation of Residual Welding Stresses in Incoloy 908 Conduit during the Jacketing of Superconducting Cables

  • Lee, Ho-Jin;Kim, Ki-Baik;Nam, Hyun-Il
    • Progress in Superconductivity and Cryogenics
    • /
    • v.5 no.1
    • /
    • pp.71-75
    • /
    • 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.

Structure of a Plasma Ion Source for a Cross-Section SEM Sample (SEM 단면 시료 제작을 위한 플라즈마 이온원의 구조)

  • Won, Jong-Han;Jang, Dong-Young;Park, Man-Jin
    • Journal of the Korean Society of Manufacturing Technology Engineers
    • /
    • v.24 no.4
    • /
    • pp.400-406
    • /
    • 2015
  • This study researched the structure of the source of an ion milling machine used to fabricate a scanning electron microscope (SEM) sample. An ion source is used to mill out samples of over 1 mm dimension using a broad ion beam to generate plasma between the anode and cathode using a permanent magnet. To mill the sample in the vacuum chamber, the ion source should be greater than 6 kV for a positive ion current over $200{\mu}A$. To discover the optimum operating conditions for the ion miller, the diameter of the extractor, anode shape, and strength of the permanent magnet were varied in the experiments. A silicon wafer was used as the sample. The sputter yield was measured on the milled surface, which was analyzed using the SEM. The wafer was milled by injecting 1 sccm of argon gas into the 0.5 mTorr vacuum chamber.

Assembly and Test of the In-cryostat Helium Line for KSTAR (KSTAR 저온용기 내부의 헬륨라인 설치 및 검사)

  • Bang, E.N.;Park, H.T.;Lee, Y.J.;Park, Y.M.;Choi, C.H.;Bak, J.S.
    • Journal of the Korean Vacuum Society
    • /
    • v.16 no.2
    • /
    • pp.153-159
    • /
    • 2007
  • In-cryostat helium lines are under installation to transfer a cryogenic helium into cold components in KSTAR device. In KSTAR, three kinds of helium should be supplied into the cold components, which are supercritical helium Into superconduction(SC) magnet system, liquid helium into current lead system, and gas helium into thermal shields. Cryogenic helium lines consist of transfer lines outside the cryostat, in-cryostat helium lines, and electrical breaks. In-cryostat helium lines should be guaranteed of leak tightness for tong time operation at high internal helium pressure of 20 bar. We wrapped the helium line with multi-layer insulator(MLI) to reduce radiation heat and insulated the surface of the high potential part with prepreg tape. The electrical break was fabricated by brazing ceramic tube with stainless steel tube. To ensure the operation reliability at operation temperature, all the electrical break have been examined by the thermal cycle test at liquid nitrogen and by the hydraulic test at 30 bar. And additional surface insulation was prepared with prepreg tape to give structural safety. At present most of the in-cryostat helium lines have been installed and the final inspection test is progressing.