• Proceedings of the Korean Vacuum Society Conference
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• 2013.08a
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• pp.179.2-179.2
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• 2013

A large-area RF-driven ion source is being developed at Germany for the heating and current drive of ITER device. Negative hydrogen ion sources are major components of neutral beam injection (NBI) systems in future large-scale fusion experiments such as ITER and DEMO. The RF sources for the production of positive hydrogen ions have been successfully developed at IPP (Max-Planck-Institute for Plasma Physics), Garching, for the ASDEX-U and W7-AS neutral beam heating systems. Ion sources of the first NBI system (NBI-1) for the KSTAR tokamak have been developed successfully with a bucket plasma generator based on the filament arc discharge, which have contributed to achieve a good plasma performance such as 15 sec H-mode operation with an injection of 3.5 MW NB power. There is a development plan of RF ion source at the KAERI to extract the positive ions, which can be used for the second NBI system (NBI-2) of the KSTAR and to extract the negative ions for future fusion devices such as Fusion Neutron Source and Korea-DEMO. The development progresses of RF ion source at the KAERI are described in this presentation.

• Proceedings of the Korean Vacuum Society Conference
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• 2010.08a
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• pp.1-1
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• 2010

핵융합에너지는 1930년대 한스 베테에 의해 태양과 별 에너지의 근원임이 밝혀진 후 소핵 폭탄실험 성공으로 그 위력적인 에너지를 인공적으로 만들 수 있음을 세상에 드러내게 된다. 그 뒤 이 에너지의 평화적인 이용 노력이 시작되었고 1958년 스위스에서 핵융합에너지의 평화적 이용에 대한 첫 국제회의가 열리게 되면서 에너지원으로서의 연구를 통해 냉전시대의 경쟁 대상의 과학기술의 하나로 부각되면서 눈부신 성능 향상을 보여주게 되었다. 아직 여러 어려운 관문이 남아있지만 기후변화와 에너지원 고갈에 의한 새로운 에너지원에 대한 강력한 필요성이 제기되면서 ITER와 같은 대형 국제공동연구시설 건설이 시작되었고 2030년대에는 최초의 핵융합발전소를 건설하려는 꿈도 그려가고 있다. 핵융합에너지를 얻는 방식에는 여러 방법이 시도되었는데 현재는 자기장을 이용해 플라즈마를 핵융합반응이 일어나기에 충분한 시간동안 가두는 자기핵융합방식과 관성으로 플라즈마를 가두는 관성핵융합방식으로 크게 구분할 수 있다. 자기핵융합방식의 경우 플라즈마를 만들고 가열하여 핵융합반응 확률이 높은 고온으로 가열하고 그 조건을 오래 지속시키는 기술들이 필요한데 이 기술들은 오늘날의 거의 모든 극한기술들이 망라되어 적용되는데 초전도, 고주파/ 초고주파, 대전력 공급, 대형 시설 실시간 제어기술, 대규모 신호처리기술, 고온 플라즈마 진단 기술, 대규모 시스템 시뮬레이션 기술 등이 그것이다. 여기에 또한 중요한 기술의 하나로 초고진공 기술이 필요하다. 이러한 기술이 집약되고 서로 통합되어 하나의 목적을 위해 쓰여지도록 고안되고 만들어진 장치가 자기핵융합 장치이며 따라서 현대의 자기핵융합장치들은 굉장히 복잡하며 대형 시설로 지어질 수밖에 없다. 우리나라는 1970년대 말부터 소형의 플라즈마 연구시설을 시작으로 자기핵융합 연구를 시작하면서 인력 양성을 시작하였으며 가속기 등 대형 연구시설이 본격적으로 지어지던 1990년대에 세계적으로 유래가 없는 초전도 자기핵융합장치인 KSTAR장치 건설 프로젝트를 시작하게 되었다. 총 11년이 넘는 건설기간 동안 여러 학교와 연구기관, 그리고 산업체가 참여하여 성공적으로 시운전을 실시하였으며 당당히 세계적인 장치를 통한 핵융합연구 대열에 동참하게 되었다. 이를 통한 기술 개발의 결과로 국제적 공동연구장치 ITER의 건설사업에 참여하게 되었고 KSTAR와 ITER를 통해 핵융합 에너지 상용화 기술 개발을 국가적인 기술개발의 목표로 결정하고 연구개발계획을 전략적으로 세워 진행하고 있다. 이번 논문에서는 자기핵융합의 특징과 연구 동향을 통해 우리나라의 기술 수준을 조망하고 특히 진공 기술 분야와의 상호 의존적 영향 분석을 통해 공동의 발전 방향을 모색해 보려고 한다.

• Nuclear Engineering and Technology
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• v.54 no.10
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• pp.3717-3723
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• 2022

For the first time, two-dimensional temporal behavior of the edge localized mode (ELM) filament is measured in the edge tokamak plasma with a multi-channel electrical probe array (MCEP). MCEP, which has 16 floating probes (4 × 4), is mounted at the far scrape-off layer (SOL) region in the KSTAR. An electron temperature and an ion flux are measured by sideband method (SBM), which can achieve two-dimensional measurements with high time resolution. Furthermore, temporal evolutions of the electron temperature and the ion flux are obtained during the ELM occurrence. In the H-mode period, short spikes from ELM bursts are observed in measured plasma parameters, and the trend is similar to that of typical Hα signal. Interestingly, when blob-like ELM filaments crash the probe, the heat flux is significantly higher in a local region of the probe array. The results show that our probe array using the SBM can measure the ELM behavior and the plasma parameters without the effect of the stray current caused by the huge device. This study can provide valuable data needed to understand the interaction between the SOL plasma and the plasma facing components (PFCs).

• Journal of the Korean Vacuum Society
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• v.16 no.6
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• pp.483-488
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• 2007

Current feeder system (CFS) for Korea superconducting tokamak advanced research(KSTAR) project plays a role to interconnect magnet power supply (MPS) and superconducting (SC) magnets through the normal bus-bar at the room temperature(300 K) environment and the SC bus-line at the low temperature (4.5 K) environment. It is divided by two systems, i.e., toroidal field system which operates at 35 kA DC currents and poloidal field system wherein 20$\sim$26 kA pulsed currents are applied during 350 s transient time. Aside from the vacuum system of main cryostat, an independent vacuum system was constructed for the CFS in which a roughing system is consisted by a rotary and a mechanical booster pump and a high vacuum system is developed by four cryo-pumps with one dry pump as a backing pump. A self interlock and its control system, and a supervisory interlock and its control system are also established for the operational reliability as well. The entire CFS was completely tested including the reliability of local/supervisory control/interlock, helium gas leakage, vacuum pressure, and so on.

• Proceedings of the Korean Vacuum Society Conference
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• 2012.08a
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• pp.269-269
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• 2012

A new ion source has been designed, fabricated, and installed at the NBTS (Neutral Beam Test Stand) at the KAERI (Korea Atomic Energy Research Institute) site. The goalis to provide a 100 keV, 2MW deuterium neutral beam injection as an auxiliary heating of KSTAR (Korea Super Tokamak Advanced Research). To cope with power demand, an ion current of 50 A is required considering the beam power loss and neutralization efficiency. The new ion source consists of a magnetic cusp bucket plasma generator and a set of tetrode accelerators with circular copper apertures. The plasma generator for the new ion source has the same design concept as the modified JAEA multi-cusp plasma generator for the KSTAR prototype ion source. The dimensions of the plasma generator are a cross section of $59{\times}25cm^2$ with a 32.5 cm depth. The anode has azimuthal arrays of Nd-Fe permanent magnets (3.4 kG at surface) in the bucket and an electron dump, which makes 9 cusp lines including the electron dump. The discharge properties were investigated preliminarily to enhance the efficiency of the beam extraction. The discharge of the new ion source was mainly controlled by a constant power mode of operation. The discharge of the plasma generator was initiated by the support of primary electrons emitted from the cathode, consisting of 12 tungsten filaments with a hair-pin type (diameter = 2.0 mm). The arc discharge of the new ion source was achieved easily up to an arc power of 80 kW (80 V/1000 A) with hydrogen gas. The 80 kW capacity seems sufficient for the arc power supply to attain the goal of arc efficiency (beam extracted current/discharge input power = 0.8 A/kW). The accelerator of the new ion source consists of four grids: plasma grid (G1), gradient grid (G2), suppressor grid (G3), and ground grid (G4). Each grid has 280 EA circular apertures. The performance tests of the new ion source accelerator were also finished including accelerator conditioning. A hydrogen ion beam was successfully extracted up to 100 keV /60 A. The optimum perveance is defined where the beam divergence is at a minimum was also investigated experimentally. The optimum hydrogen beam perveance is over $2.3{\mu}P$ at 60 keV, and the beam divergence angle is below $1.0^{\circ}$. Thus, the new ion source is expected to be capable of extracting more than a 5 MW deuterium ion beam power at 100 keV. This ion source can deliver ~2 MW of neutral beam power to KSTAR tokamak plasma for the 2012 campaign.

• Proceedings of the Korean Vacuum Society Conference
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• 2007.02a
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• pp.197-197
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• 2007

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.703-704
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• 2004

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.717-718
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• 2004

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.705-706
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• 2004

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.727-728
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• 2004