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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.
Quench Protection System for the KSTAR Toroidal Field Superconducting Coil
Lee, Dong-Keun,Choi, Jae-Hoon,Jin, Jong-Kook,Hahn, Sang-Hee,Kim, Yaung-Soo,Ahn, Hyun-Sik,Jang, Gye-Yong,Yun, Min-Seong,Seong, Dae-Kyoung,Shin, Hyun-Seok The Korean Institute of Electrical Engineers 2012 Journal of Electrical Engineering & Technology Vol.7 No.2
The design of the integrated quench protection (QP) system for the high current superconducting magnet (SCM) has been fabricated and tested for the toroidal field (TF) coil system of the Korea Superconducting Tokamak Advanced Research (KSTAR) device. The QP system is capable of protecting the TF SCM, which consists of 16 identical coils serially connected with a stored energy of 495 MJ at the design operation level at 35.2 kA per turn. Given that the power supply for the TF coils can only ramp up and maintain the coil current, the design of the QP system includes two features. The first is a basic fast discharge function to protect the TF SCM by a dump resistor circuit with a 7 s time constant in case of coil quench event. The second is a slow discharge function with a time constant of 360 s for a daily TF discharge or for a stop demand from the tokamak control system. The QP system has been successfully tested up to 40 kA with a short circuit and up to 34 kA with TF SCM in the second campaign of KSTAR. This paper describes the characteristics of the TF QP systems and test results of the plasma experiment of KSTAR in 2009.
Development of In-Vessel Vertical Coil Power Supply in KSTAR
Jong-Kook Jin,Jae-Hoon Choi,Dong-Keun Lee,Sang-Hee Han,Young-Mu Jeon,Yaung-Su Kim,Myeun Kwon,Hyun-Sik Ahn,Gye-Yong Jang,Min-Seong Yun,Dae-Kyung Seong,Hyun-Seok Shin IEEE 2013 IEEE transactions on plasma science Vol.41 No.7
<P>The Korea Superconducting Tokamak Advanced Research (KSTAR) device is an advanced superconducting tokamak to establish scientific and technological bases for an attractive fusion reactor [1]. In-vessel vertical coil (IVC) power supply (PS) is developed for vertical stability and shape control of KSTAR plasma. IVC PS in KSTAR is based on a single-phase full-bridge inverter. The output voltage and current are dc ±1 kV and ±10 kA, respectively. Insulated gate bipolar transistor is used as switching power device in IVC PS and maximal 5 kHz of switching frequency is adopted to meet the requirement of fast control by plasma control system. This paper describes the configuration and engineering of the IVC PS system and analyzes both the IVC coil commissioning and the major performances that D-shape plasma achieved in experiments.</P>
유한 효과에 의한 Gadolinium 박막의 Curie온도 이동
Rhee, Il-Su,Chu, Gyo-Jin,Lee, Eui-Wan,Lee, Sang-Yun,Lee, Chong-Yong,Kim, Yaung-Soo,Kim, Dong-Lak,Ri, H.C. 한국재료학회 1994 한국재료학회지 Vol.4 No.6
자화도를 측정함으로써 gadolinium박막의 강자성에서 상자성으로의 전이온도를 결정했다. 박막의 전이온도는 박막의 두께가 얇아짐에 따라 점점 더 bulk계의 전이온도보다 낮아지는 것이 관측되었으며 이 현상은 박막계의 유한성에 의해 일어나는 현상으로 알려져 있다. 우리는 이 결과를 유한효과 및 유한 축척이론에 근거하여 설명하였다. We determine the Curie temperature of thin gadolinium films by the measurement of magnetization as a function of temperature. From these data, we observe the Curie temperature shift in films from the bulk value, and also see the systematic behavior of this shift with thicknesses of films, that is, the larger the shift is, the thinner the film is. In this paper, we analyze and explain these results in light of finite-size scaling theory.
CURRENT STATUS OF NUCLEAR FUSION ENERGY RESEARCH IN KOREA
Kwon, My-Eun,Bae, Young-Soon,Cho, Seung-Yon,Choe, Won-Ho,Hong, Bong-Geun,Hwang, Yong-Seok,Kim, Jin-Yong,Kim, Kee-Man,Kim, Yaung-Soo,Kwak, Jong-Gu,Lee, Hyeon-Gon,Lee, San-Gil,Na, Yong-Su,Oh, Byung-Hoon Korean Nuclear Society 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.
세륨연마재 폐슬러리 건조분말로부터 희토류와 알루미늄의 분리
윤호성,김철주,김성돈,이진영,조성욱,김준수,Yoon Ho-Sung,Kim Chul-Joo,Kim Sung-Don,Lee Jin-Yaung,Cho Sung-Wook,Kim Joon-Soo 한국자원리싸이클링학회 2003 資源 리싸이클링 Vol.12 No.5
본 연구에서는 세륨연마재 폐슬러리 건조분말로부터 세륨을 포함한 희토류성분과 알루미늄을 분리하고자 하였다. 출발원료인 세륨연마재 폐슬러리 건조분말의 희토류 중에는 산화세륨이 전체 희토류 성분의 약 40% 정도 함유되어 있는데, 산화세륨은 희토류원소들 중에서 가장 안정된 형태로 이에 대한 분해가 용이하지 않다. 그러므로 황산화반응을 이용하여 산화세륨을 분해하므로써 희토류의 분리ㆍ회수율을 향상시키고자 하였으며, 침출용액으로부터 희토류와 알루미늄을 분리하기 위하여, 희토류 원소들은 황산매질에서 황산나트륨과 반응하여 황산나트륨희토류(ReㆍNa($SO_4$)$_2$)를 형성하면서 침전되는 특성을 이용하였으며 쉽게 희토류와 알루미늄을 분리할 수 있었다. In this study, the separation of rare earths and aluminium from the dried powder of waste cerium polishing slurry was investigated. Since cerium oxide, 40% of rare earths, is the most stable state in rare earth, the dissolution of cerium oxide in acid solution is not easy. Therefore the dissolution process of cerium oxide by sulfation was examined in order to increase the recovery of rare earth. The rare earths could be separated from aluminum by double salt precipitation using sodium sulfate.