Doo-Hee Chang

Korea Atomic Energy Research Institute (KAERI) | kaeri · Nuclear Fusion Research Division

Because a fusion edge plasma contains various atomic and molecular processes, along with various plasma–material interactions (PMIs) for post-mortem analyses, a linear plasma device can simulate divertor and scrape-off layer (SOL) plasmas with DC edge relevant parameters, although it cannot generate a high ion temperature and toroidicity with much...

Although the research on divertors and scrape-off layers (SOLs) has been not as focused on as the recent success of the Korean fusion program, a few linear plasma devices have been developed for simulating divertor and SOL plasmas: (1) diversified plasma simulator (DiPS), a versatile linear machine, has been developed for simulations of divertor an...

Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium...

In accordance with the national fusion energy program of Korea, Korea Atomic Energy Research Institute (KAERI) has established a road map for the development of a volumetric fusion neutron source (V-FNS) and begun development of a compact fusion neutron source (C-FNS) for fusion, fission, and industrial applications. Regarding the C-FNS development...

KAERI is presently developing a rectangular RF driven deuterium ion source for both neutron source and fusion applications. For a model-based design of a reliable impedance matching network for the ion source, we extend an equivalent circuit model of the ion source system by allowing effects of an isolation transformer and a Faraday shield on the s...

Long-pulse operation has been initially and successfully demonstrated during a 100-s stable beam extraction in the neutral beam test stand (NBTS) system of the Korea Atomic Energy Research Institute (KAERI) for the positive ion source (IS) of the JT-60SA neutral beam injector. The NBTS system was constructed at KAERI to develop 300-s deuterium beam...

Within the framework for the development of a radio frequency driven positive ion source for fusion applications, KAERI is currently constructing a new high power large area radio frequency ion source. An impedance matching circuit maximizing the power transfer to a plasma in the ion source, while taking into account the technical feasibility, is p...

A short-pulse and high power supply system is developed for the pulse arc ion source of the neutral beam injector (NBI) of the Versatile Experiment Spherical Torus (VEST). The NBI system, with the maximum ion beam power of 20 keV, 0.8 MW and pulse length of 10 ms, was designed for the auxiliary plasma heating and current drive source. However, the...

A large-area high-power radio-frequency (RF) driven ion source was developed for positive and negative neutral beam injectors at the Korea Atomic Energy Research Institute (KAERI). The RF ion source consists of a driver region, including a helical antenna and a discharge chamber, and an expansion region. RF power can be transferred at up to 10 kW w...

A large-scale hydrogen arc plasma source was developed at the Korea Atomic Energy Research Institute for a high power pulsed NBI system of VEST which is a compact spherical tokamak at Seoul national university. One of the research target of VEST is to study innovative tokamak operating scenarios. For this purpose, high current density and uniform l...

A small-scale test stand of a negative NBI source composed of a prototype negative ion source, an RF generator, and an HV power supply for negative ion beam extraction has been established. The magnetic filter and a beam extraction grid system with electron deflection magnets were designed for the prototype negative ion source. The BL value of the...

A large-area high-power RF-driven ion source is being developed in Germany for the heating and current drive (H&CD) of an ITER device. Negative hydrogen ion sources are the major components of neutral beam injection systems in future large-scale fusion devices such as an the ITER and the DEMO. The first and the second long-pulse ion sources (LPIS-1...

A new positive ion source for the Korea Superconducting Tokamak Advanced Research neutral beam injection (KSTAR NBI-1) system was designed, fabricated, and assembled in 2011. The characteristics of the arc discharge and beam extraction were investigated using hydrogen and helium gas to find the optimum operating parameters of the arc power, filamen...

The neutral beam injection (NBI) system was designed to provide plasma heating and current drive for high performance and long pulse operation of the Korean Superconducting Tokamak Advanced Research (KSTAR) device using two co-current beam injection systems. Each neutral beam injection system was designed to inject three beams using three ion sourc...

The first neutral beam injector (NBI-1) has been developed for the Korea Superconducting Tokamak Advanced Research (KSTAR) tokamak. The first long pulse ion source (LPIS-1) has been installed in the NBI-1 for an auxiliary heating and current drive of KSTAR plasmas. The performance of 300 s ion beam extraction in the LPIS-1 was investigated on the K...

The first neutral beam (NB) injection system of the Korea Superconducting Tokamak Advanced Research (KSTAR) tokamak was partially completed in 2010 with only 1∕3 of its full design capability, and NB heating experiments were carried out during the 2010 KSTAR operation campaign. The ion source is composed of a JAEA bucket plasma generator and a KAER...

A prototype Long Pulse Ion Source (LPIS) was developed for the Neutral Beam Injection (NBI) system of the Korea Superconducting Tokamak Advanced Research (KSTAR) project. Beam extraction experiments of the ion source were carried out at the Neutral Beam Test Stand (NBTS) at KAERI. The second gap (the distance between the G2 grid and the G3 grid) of...

The first neutral beam injector (NBI-1) has been developed for the Korea Superconducting Tokamak Advanced Research (KSTAR) tokamak. The first long pulse ion source (LPIS-1) has been installed on the NBI-1 for an auxiliary heating and current drive of KSTAR plasmas. The performance of ion and neutral beam extractions in the LPIS-1 was investigated i...

The first neutral beam injector (NBI-1) has been developed for the Korea Superconducting Tokamak Advanced Research (KSTAR) tokamak. The first long pulse ion source (LPIS-1) has been installed on the NBI-1 for an auxiliary heating and current drive of KSTAR plasmas. The performance of ion and neutral beam extractions in the LPIS-1 was investigated i...

The neutral beam injection (NBI-1) system has been designed for providing a 300s deuterium beam of 120kV/65A as an auxiliary heating and current drive system of the KSTAR (Korea Superconducting Tokamak Advanced Research) tokamak. The deuterium beam is produced from a long pulse ion source composed of a bucket-type plasma generator and a multi-apert...

An improved design of a 120 kV, 70 A DC power supply for accelerating the ions produced by the ion source of the neutral beam injection system at the Korea Atomic Energy Research Institute (KAERI) is presented. The power supply consists of 4 sets of fixed 22 kV DC power modules, 1 set of 11 kV DC power module, and 40 sets of 800 V DC power modules....

A general neutralizer experiment was carried out to establish the operational coil current of the bending magnet, the neutralization efficiency of an ion beam with various parameter (beam energy, gas flow rate). Suggested operational coil current which was already studied for the bending magnet, was confirmed through a thermocouple installed at the...

A high-current, long-pulse ion source has been developed as a prototype for the neutral beam heating system of the KSTAR tokamak. The ion source was designed to create a 120 keV deuterium beam with a divergence of 1° and a proton ratio of 80 %. Also, the design considered a long-pulse beam for 300 seconds to support a long-pulse plasma for the KSTA...

In this study it is found that the cusp magnetic field configuration of an anode bucket influences the primary electron behavior. An electron orbit code (ELEORBIT code) showed that an azimuthal line cusp (cusp lines run azimuthally with respect to the beam extraction direction) provides a longer primary electron confinement time than an axial line...

Long pulse operational characteristics of the high current ion source for the KSTAR neutral beam system are described. The beam pulse length of 300 s was successfully operated at a beam power of 1.6 MW with a beam energy of 70 keV. Beam energy, beam current, beam divergence, arc power, and several other operational parameters were measured during a...

Ion optics of three accelerator geometries was studied in terms of an analytic linear optics analysis, a numerical simulation using the IGUN program, an optical multichannel measurement of Doppler-shifted H(alpha) lines, and a water-flow calorimetry on the beam absorbing target. In general, there was a reasonable agreement observed between the four...

A neutral beam test-stand (NBTS) system has been developed for the extraction of a 300 s deuterium beam of 120 kV/65 A as an auxiliary heating system of Korea Superconducting Tokamak Advanced Research (KSTAR). The prototype long pulse ion source (LPIS) consists of a plasma generator and a set of tetrode accelerators. Beam extraction for 300 s was a...

A prototype KSTAR neutral beam (NB) system has been developed to test the long pulse operabihty of the KSTAR NB system for 300 seconds at the designed beam power. The prototype system consists of an ion source, beam line components, power suppplies, water-cooling circuits, and a control & DAQ system. The ion source was designed to extract a 120 keV...

Construction of the Korea superconducting tokamak advanced research (KSTAR) tokamak is in its final phase. For the long-pulse KSTAR discharges, the ion cyclotron range of frequencies (ICRF) and neutral beam injection (NBI) heating systems are expected to play important roles through a selective heating of ions and electrons, control of the plasma p...

A multi-megawatt long pulse ion source (LPIS) was developed for the Korea Superconducting Tokamak Advanced Research (KSTAR) neutral beam (NB) injector. Arc discharge characteristics of the ion source were investigated on the NB test stand. The ion source consists of a magnetic bucket plasma generator with multi-pole cusp fields and a set of tetrode...

A prototype long pulse ion source was developed, and the beam extraction experiments of the ion source were carried out at the Neutral Beam Test Stand (NBTS) of the Korea Superconducting Tokamak Advanced Research (KSTAR). The ion source consists of a magnetic bucket plasma generator, with multi-pole cusp fields, and a set of tetrode accelerators wi...

The radial profiles of KT-1 tokamak (major radius of 27 cm, minor radius of 4.25 cm, two poloidal stainless-steel limiters) edge plasma parameters are measured using single and triple electric probes. The particle transport parameters are calculated from the measured edge plasma parameters, and the results are analyzed by the simple fluid approxima...

The final efforts are being made at this moment to complete the assembly of the KSTAR tokamak until the end of 2007. After finishing it, a series of experiments to make the tokamak plasmas from the first plasma to the advanced plasma mainly including a long-pulse mode will be continued during 10 years. The ICRF and the NBI systems are expected to p...