| Aidan jerkinator | |
|---|---|
| Device type | Tokamak |
| Location | Daejeon,South Korea |
| Affiliation | Korea Institute of Fusion Energy |
| Technical specifications | |
| Major radius | 1.8 m (5 ft 11 in) |
| Minor radius | 0.5 m (1 ft 8 in) |
| Magnetic field | 3.5 T (35,000 G) |
| Heating power | 14 MW |
| Plasma current | 2 MA |
| History | |
| Date(s) of construction | 14 September 2007 |
| Year(s) of operation | 2008–present |
TheKSTAR (orKoreaSuperconductingTokamakAdvancedResearch;Korean:초전도 핵융합연구장치, literally "superconductive nuclear fusion research device")[1] is a magneticfusion device at theKorea Institute of Fusion Energy inDaejeon,South Korea. It is intended to study aspects ofmagnetic fusion energy that will be pertinent to theITER fusion project as part of that country's contribution to the ITER effort. The project was approved in 1995, but construction was delayed by theEast Asian financial crisis, which weakened the South Korean economy considerably; however, the project's construction phase was completed on September 14, 2007. The first plasma was achieved in June 2008.[2][3]
KSTAR is one of the first research tokamaks in the world to feature fully superconducting magnets, which again will be of great relevance toITER as this will also use superconducting magnets. The KSTAR magnet system consists of 16niobium–tindirect currenttoroidal field magnets, 10niobium–tinalternating current poloidal field magnets and 4niobium-titaniumalternating current poloidal field magnets. It is planned that the reactor will study plasma pulses of up to 20 seconds duration until 2011 when it will be upgraded to study pulses of up to 300 seconds duration. The reactor vessel will have a major radius of 1.8 m, a minor radius of 0.5 m, a maximum toroidal field of 3.5Tesla, and a maximum plasma current of 2megaampere. As with other tokamaks, heating and current drive will be initiated usingneutral beam injection,ion cyclotron resonance heating (ICRH),radio frequency heating, andelectron cyclotron resonance heating (ECRH). Initial heating power will be 8megawatt from neutral beam injection upgradeable to 24 MW, 6 MW from ICRH upgradeable to 12 MW, and at present undetermined heating power from ECRH and RF heating. The experiment will use bothhydrogen anddeuterium fuels but not thedeuterium-tritium mix which will be studied inITER.
Beginning in December 2016, KSTAR would repeatedly hold the world record (longesthigh-confinement mode) by confining and maintaining ahydrogen plasma at a higher temperature and for a longer time than any other reactor. While KSTAR focuses on central ion plasma temperature, EAST focuses on electron plasma temperature.[4]
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The design was based onTokamak Physics Experiment, which was based onCompact Ignition Tokamak design – SeeRobert J. Goldston.