http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
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.
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.
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>