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Research

Research

About KSTAR

The goal of KSTAR is to build a steady-state-capable advanced superconducting tokamak to establish scientific and technological basis for a fusion reactor. Through international collaboration with the fusion community and domestic industry, KSTAR was born to lay the foundation for advanced fusion research.

During previous research campaigns, the KSTAR achieved unprecedented superconducting tokamak operation with astonishing results, of a long-pulse H-mode, a high ion temperature exceeding 100 million degrees, and reliable ELM (edge localized mode) suppression.

KSTAR continues to achieve key technologies and physics understanding toward the dream of a commercial fusion reactor with the collaboration of the fusion community.

KSTAR System Specification

Final target performance: Toroidal magnetic field_3.5 Tesla, Plasma pulse duration of 300 seconds, superconducting operating temperature_4K (269 degrees below zero)

KSTAR Mission & Progress

Misson

  • To achieve the superconducting tokamak construction and operation experiences

KSTAR Key Features

Highly efficient tokamak

  • middle size & mega-ampere class

Steady-state & ITER relevant device

  • Nb3Sn superconducting magnet
  • active cooled in-vessel components
  • long-pulse non-inductive heating and current drive

High performance operational capability

  • passive stabilizer
  • in-vessel control coils
  • strong shaping
Schematics of the KSTAR device

Schematics of the KSTAR device

KSTAR Parameters

KSTAR Parameters
PARAMETERS KSTAR ITER
Major radius, R0 1.8 m 6.2 m
Minor radius, a 0.5 m 2.0 m
Elongation, k 2.0 1.7
Triangularity, δ 0.8 0.33
Plasama volume 17.8 ㎥ 830 ㎥
Plasama surface area 56 ㎡ 680 ㎡
Plasama cross section 1.6 ㎡ 22 ㎡
Plasama shape DN, SN SN
Plasama current, lP > 2.0 MA 15 (17) MA
Toroidal field, B0 > 3.5 T 5.3 T
Pulse length > 300 s 400 s
βN ~ 5.0 1.8 (2.5)
Plasma fuel H, D-D H, D-T
Superconductor Nb3Sn, NbTi Nb3Sn, NbTi
Auxiliary heating /CD ~ 28 MW 73 (110) MW
Cryogenic 9 kW @4.5K
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