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- 저자 : Keeman Kim (검색결과 78 건)
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Present Status of the KSTAR Superconducting Magnet System Development
keeman kim,A. Chertovskikh,B.S. Lim,C.S. Kim,D.J. Kim,D.K. Lee,G.S. Lee,H. Yonekawa,H.J. Lee,H.K. Park,I.S. Woo,J.S. Park,J.S. Kim,J.Y. Choi,K.P. Kim,K.R. Park,M.K. Kim,N.H. Song,S.H. Baek,S.I. Lee,S. 한국물리학회 2004 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.44 No.52
The mission of korea superconducting tokamak advanced research (KSTAR) Project is to develop a steady-state-capable advanced superconducting tokamak for establishing a scientic and technological basis for an attractive fusion reactor. Because the KSTAR mission includes the achievement of a steady-state-capable operation, the use of superconducting coils is an obvious choice for the magnet system. The KSTAR superconducting magnet system consists of 16 TF (toroidal eld) and 14 PF (poloidal eld) coils. Both of the TF and the PF coil systems use internally cooled cable-in-conduit conductors (CICC). The TF coil system provides a eld of 3.5 T at the plasma center, and the PF coil system is able to provide a ux swing of 17 V-sec. The major achievements in the KSTAR magnet system development include the development of CICC, the development of a full-size TF model coil, the development of a background magnetic eld generation coil system, and the construction of a large-scale superconducting magnet and CICC test facility. The TF and The PF coils are being fabricated for the KSTAR completion in the year 2005.
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(Review Article) Status of the KSTAR Project
KIM, Keeman,OH, Yeong-Kook,S. BAK, Joo,KWON, Myeun,LEE, Gyung-Su,KSTAR team, The 低溫工學協會 2006 低溫工學 Vol.41 No.5
<P>The KSTAR project was started in 1996 and conducted in three phases, the conceptual design phase (1996-1998), the R&D and engineering design phase (1998-2002), and the construction phase (2002-2007). The mission of the Korea Superconducting Tokamak Advanced Research (KSTAR) Project is to develop a steady-state-capable advanced superconducting tokamak for establishing a scientific and technological basis for an attractive fusion reactor. Since the KSTAR mission includes the achievement of a steady-state-capable operation, the use of superconducting coils is an obvious choice for the magnet system and the long pulse current drive and heating systems are also the important aspect of the KSTAR design features. The advanced tokamak aspect of the mission is incorporated in the design features associated with flexible plasma shaping, double-null divertor and passive stabilizer, internal control coils. All the major components are in the stage of the fabrication and assembly for the completion of the KSTAR construction in the year 2007.</P>
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Conceptual design study of the K-DEMO magnet system
Kim, Keeman,Oh, Sangjun,Park, Jong Sung,Lee, Chulhee,Im, Kihak,Kim, Hyung Chan,Lee, Gyung-Su,Neilson, George,Brown, Thomas,Kessel, Charles,Titus, Peter,Zhai, Yuhu Elsevier 2015 Fusion engineering and design Vol.96 No.-
<P><B>Abstract</B></P> <P>As the ITER is being constructed, there is a growing anticipation for an earlier realization of fusion energy. A major design philosophy for the initiated conceptual design study for a steady-state Korean fusion demonstration reactor (K-DEMO) is engineering feasibility. A two-staged development plan is envisaged. K-DEMO is designed not only to demonstrate a net electricity generation and a self-sustained tritium cycle, but also to be used, in its initial stage, as a component test facility. Then, in its second stage, a major upgrade is carried out by replacing in-vessel components in order to show a net electricity generation on the order of 500MWe. After a thorough 0-D system analysis, the major radius and minor radius are chosen to be 6.8m and 2.1m, respectively. In order to minimize wave deflection, a top-launch high frequency (>200GHz) electron cyclotron current drive (ECCD) system will be the key system for the current profile control. For matching the high frequency ECCD, a high toroidal field (TF) is required and can be achieved by using high current density Nb<SUB>3</SUB>Sn superconducting conductor. The peak magnetic field reaches to 16T with the magnetic field at the plasma center above 7T. Key features of the K-DEMO magnet system include the use of two TF coil winding packs, each of a different conductor design, to reduce the construction cost and save the space for the magnet structure material.</P> <P><B>Highlights</B></P> <P> <UL> <LI> Perform a preliminary conceptual study for a steady-state Korean DEMO reactor. </LI> <LI> Present a preliminary design of TF (toroidal field) magnet. </LI> <LI> Present a preliminary design of CS (central solenoid) magnet. </LI> <LI> Present a preliminary design of PF (toroidal field) magnet. </LI> </UL> </P>
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Jiman Kim,Kihong Sim,Kyeongho Jang,Sanghyun Je,Pyeongyeol Park,Sangjun Oh,Keeman Kim IEEE 2008 IEEE transactions on applied superconductivity Vol.18 No.2
<P>Nb<SUB>3</SUB>Sn strands which will be used for the ITER TF coils should be chrome plated thickness of 1.8 mum to reduce AC loss and improve the thermal stability of cable. During heat treatment, the RRR value can be affected by Cr diffusion. In this work, the effect of Cr diffusion was systematically studied, using the KSTAR and ITER candidate strands. For the KSTAR strand, the Cu/non-Cu ratio was systematically varied from 1.53 to 0.69 by chemical etching whereas the samples were heat treated by the same schedule. For the ITER candidate strand, on the other hand, the Cu/non-Cu ratio was fixed to the specification value of 1.0, and the variation of the RRR value was studied with respect to the heat treatment schedule, especially the retention time of the 650degC plateau was varied from 100 to 200 hours. It was also compared with the Cr diffusion distance obtained from EPMA (electron probe microanalysis). We found that the RRR value of the ITER candidate strand becomes lower than the ITER requirement of 100, if the heat treatment at 650degC is longer than 200 hours. The RRR can be reached up to 161 when the duration of 650degC plateau is reduced to 100 hours, while satisfying all other ITER requirements including the critical current density.</P>
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Development and Sultan Test Result of ITER Conductor Samples of Korea
Hyoung Chan Kim,Dong Keun Oh,Soo-Hyeon Park,Keeman Kim,Bruzzone, P. IEEE 2008 IEEE transactions on applied superconductivity Vol.18 No.2
<P>As a way to improve performance of ITER TF conductors, two types of cable-in-conduit conductors were developed in Korea with variations of conduit thickness resulting in the different void fraction of the conductors. The estimated void fractions of the conductors are 31% and 33%. Here we report the details of the TF conductor development and the performance test result of them carried out in SULTAN. Regarding the conductor development, the internal-Sn-processed strand characteristics, strand cabling, twist pitch and characteristics of the conduits for the conductors are presented. For an extended understanding of the conductor design and performance, the SULTAN test results are presented and the effect of the void fraction variations is discussed based on the results.</P>
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프랙탈 난류생성판을 사용한 예혼합 V-shape 화염에서 두 가지 난류 연소속도 조사
김주한(Juhan Kim),김정현(Junghyeon Kim),이기만(Keeman Lee) 한국연소학회 2021 KOSCOSYMPOSIUM논문집 Vol.2021 No.11
This study focused on the turbulent burning velocity, which is one of the characteristics of turbulent V –shape combustion using a fractal turbulence generated plate. The local displacement speed and local consumption speed were investigated as the turbulent burning velocities obtained from V-shape turbulent flames. The fractal turbulence generator changes the pattern using shape parameters blockage ratio σ and thickness reduction ratio Rt. The two turbulent burning velocities showed a tendency to increase with the increase of σ, decrease of Rt, and increase of height after flame stabilization rod. In addition, the fractal turbulence generated plate showed a significantly increased turbulent burning velocity than the general perforated plate type.
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CURRENT STATUS OF NUCLEAR FUSION ENERGY RESEARCH IN KOREA
MYEUN KWON,YOUNG SOON BAE,SEUNGYON CHO,최원호,홍봉근,황용석,JIN YONG KIM,KEEMAN KIM,YAUNG-SOO KIM,JONG-GU KWAK,HYEON GON LEE,SANGIL LEE1,나용수,BYUNG-HOON OH,YEONG-KOOK OH,박지연,HYUNG LYEOL YANG,IN KEUN YU 한국원자력학회 2009 Nuclear Engineering and Technology Vol.41 No.4
The history of nuclear fusion research in Korea is rather short compared to that of advanced countries. However, since the mid- 1990s, at which time the construction of KSTAR was about to commence, fusion research in Korea has been actively carried out in a wide range of areas, from basic plasma physics to fusion reactor design. The flourishing of fusion research partly owes to the fact that industrial technologies in Korea including those related to the nuclear field have been fully matured, with their quality being highly ranked in the world. Successive pivotal programs such as KSTAR and ITER have provided diverse opportunities to address new scientific and technological problems in fusion as well as to draw young researchers into related fields. The frame of the Korean nuclear fusion program is now changing from a small laboratory scale to a large national agenda. Coordinated strategies from different views and a holistic approach are necessary in order to achieve optimal efficiency and effectiveness. Upon this background, the present paper reflects upon the road taken to arrive at this point and looks ahead at the coming future in nuclear fusion research activities in Korea.
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Kim, Jaehyeon,Jang, Munseok,Lee, Keeman,Masri, A.R. Elsevier 2019 Experimental thermal and fluid science Vol.105 No.-
<P><B>Abstract</B></P> <P>The main objective of this work was to investigate the beating behavior of acoustically self-excited instabilities in dual swirl combustors. This was achieved by measuring fluctuations in sound pressure and heat release, and analyzing the resulting frequency maps to evaluate the propensity for thermoacoustic instability. The experiments were carried out while varying the combustor length and thermal power. Consequently, the frequency map representing the sound pressure of the flame instability can be divided into two modes exhibiting different behaviors. According to the resonance frequency equation, the frequency of the thermoacoustic instability increases with the thermal power and decreases with the combustor length. In the case of Mode 1, when the thermal power is relatively high, the propensity for predominant frequencies is consistent with the trend indicated by the resonance equation. In Mode 2, on the other hand, when the thermal power is low, the frequencies remain nearly constant even when the combustor length increases. In the case of lower thermal power and longer combustor lengths, a new wave pattern is observed, in which two signals of similar cycles merge to generate a new signal. Under these conditions, the combustion intensity is approximately 2.0–3.0 MW/m<SUP>3</SUP> atm and the gradient of the combustion intensity decreases. This is caused by a beating phenomenon, which we verified by inputting the experimental results into the beating equation. We also analyzed high-speed images and measured the heat release fluctuations in the pilot flame, and confirmed that the pilot flame and main flame have different cycles, thus leading to beating.</P> <P><B>Highlights</B></P> <P> <UL> <LI> A flame behavior of instability in dual swirl combustors is observed. </LI> <LI> The frequency of acoustic instability is divided into two modes. </LI> <LI> In the case of Mode 2 and longer combustor length, a new wave pattern is observed. </LI> <LI> The non-uniform wavelength occurs in the specific combustion intensity. </LI> <LI> Beating behavior occurs due to the different fluctuation cycles of flame. </LI> </UL> </P>
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