• Journal of Technology Innovation
• /
• v.22 no.4
• /
• pp.145-164
• /
• 2014

Nuclear fusion is one of the most promising options for generating large amounts of carbon-free energy in the future. Major countries such as China, EU, and Japan have established a national plan for DEMO construction and they are implementing it. Korea has started a nuclear fusion research and development by the KSTAR project started in 1995. There are matured needs for a full-scale research and development initiatives to ensure competition with the major countries for DEMO as well as achieve the final goal to commercialize fusion energy. In this paper, we apply the TRL and AHP methods in order to identify the key technologies to conduct DEMO R&D. We propose the priorities of future R&D on DEMO by deriving a core technology in the field. At first, we review the scientific theory of fusion and trend of progress of DEMO activities in major countries. For previous studies, we review TRL and AHP methods to examine the technology classification system of DEMO and identify key technologies. We apply TRL method to identify readiness level of DEMO technologies and AHP to compensate shortcoming of TRL. The key technologies of DEMO to be secured from a synthesis result of the TRL and AHP are burning plasma, plasma facing material, structural material, high frequency heating, neutral particle beam, safety, plasma diagnostic, and simulation technologies.

• Journal of Ocean Engineering and Technology
• /
• v.15 no.3
• /
• pp.58-62
• /
• 2001

The objective of research is to clarify the interaction between dislocations and precipitates during high temperature creep deformation behaviors of high n austenitic steels. After measuring the internal stress in minimum creep rate state under applied stress of 236MPa at 873K, a transmission electron microscope (TEM) observation was performed to investigate the interaction between dislocations and precipitates during high temperature creep deformation. The band widths and values of internal stress increased when the nitride precipitates distribute more densely. Fine nitrides disturbed the dislocation movement with pinning the dislocations and perfect dislocations were separated into Shockley partial dislocations by fine nitrides. Coarse nitrides disturbed the dislocation movement with climb mechanism.

• Transactions of the Korean Society of Mechanical Engineers B
• /
• v.33 no.9
• /
• pp.643-657
• /
• 2009

This paper introduces the current nuclear experimental research activities in KAERI, the unique nuclear research institute in Korea, and the universities in Korea to solve and assess the issues which have been faced in the design of new reactors such as APR1400, SMART, GEN-IV reactors as well as fusion reactor. Also the experimental evaluations of safety for operating nuclear plants have been presented. The nuclear thermalhydraulic experiments performed in such organizations are classified the fundamental test, the separated effect test, and the integral effect test with ATLAS and SNUF. Introduction is deployed according to institutes. Finally, the future works and the direction of research voyage in the nuclear thermal-hydraulic field were suggested.

• Journal of the Korean Society for Precision Engineering
• /
• v.16 no.1 s.94
• /
• pp.238-245
• /
• 1999

For the optimal design of plasma facing components of a fusion reactor, thorough understanding of thermal behavior of high heat. nux components are required. The purpose of this research is to investigate the characteristics of heat flow and thermal stress in divertors which are exposed to high heat load varing with time and space-Numerical simulations of heat now and thermal stress for three types of diverter are performed using finite volume method and finite element method. Respectly, commercial FLUENT code are used in the heat flow simulation, and maximum surface temperature, temperature distribution and cooling rate are calculated. Commercial ABQUS code are used for calculating temperature distribution. thermal stress, strain and displacement. Through this computer simulation. design data for cooling system and Structural provided.

• Journal of Institute of Control, Robotics and Systems
• /
• v.2 no.4
• /
• pp.297-305
• /
• 1996

In this paper a novel robust adaptive fuzzy controller for the nonlinear system with state-dependent uncertainty is proposed. The conventional adaptive fuzzy controller determines the function of state variable bounding the state-dependent uncertain term in the system dynamics on the local state space by off-line calculation. Whereas the proposed method determines that function by the fuzzy inference so that it guarantees the stability of the closed loop system globally on the whole state space. In addition, the method is applicable to the multi-input system. We applied the proposed method to the Burn Control of the Tokamak fusion reactor whose dynamics contains the state-dependent uncertainty and proved the effectiveness of the scheme by using the simulation results.

• Proceedings of the KSME Conference
• /
• 2007.05a
• /
• pp.166-171
• /
• 2007

The characterization of monolithic SiC and SiCf/SiC composite materials fabricated by NITE and RS processes was investigated in conjunction with the detailed analysis of their microstructure and density. The NITE-SiC based materials were fabricated, using a SiC powder with average size of 30 nm. RS- SiCf/SiC composites were fabricated with a complex slurry of C and SiC powder. In the RS process, the average size of starting SiC particle and the blending ratio of C/SiC powder were $0.4\;{\mu}m$ and 0.4, respectively. The reinforcing materials for /SiC composites were BN-SiC coated Hi-Nicalon SiC fiber, unidirectional or plain woven Tyranno SA SiC fiber. The characterization of all materials was examined by the means of SEM, EDS and three point bending test. The density of NITE-SiCf/SiC composite increased with increasing the pressure holding time. RS-SiCf/SiC composites represented a great decrease of flexural strength at the temperature of $1000\;^{\circ}C.$

• Electrical & Electronic Materials
• /
• v.8 no.4
• /
• pp.518-525
• /
• 1995

본 고에서는 Nb$_{3}$Sn 초전도선재의 대표적인 제조방법 및 원리 그리고 고자장마그네트 설계시 중요한 요소인 Nb$_{3}$Sn의 자장중 초전도특성 및 기계적특성 등에 대하여 고찰하고자 한다. 또한 Nb$_{3}$Sn 초전도선재의 응용분야로서 몇가지 대표적인 예를 들어 현재 세계적으로 활발하게 진행되고 있는 선진국의 고자장 초전도마그네트와 관련된 연구개발동향을 소개하고자 한다.

• Proceedings of the KIPE Conference
• /
• 2014.11a
• /
• pp.44-45
• /
• 2014

본 논문은 ITER의 플라즈마 제어를 위하여 자기적으로 결합된 초전도 PF 코일에 흐르는 전류를 제어하는 기법과 RTDS 실험결과를 분석하였다. MATLAB/SIMULINK를 이용하여 유도 결합된 4개의 초전도코일을 모델링하여 전류제어기법을 시뮬레이션하였으며, 실험은 RTDS를 이용하여 진행하였다. 각 부하전류가 전류 지령치를 추종할 때, 동시다발적으로 발생하는 상호 인덕턴스와 전류 극성변화의 영향을 MIMO(Multi Input Multi Output) 시스템 기반으로 하여 각 초전도코일의 전압변화 특성을 해석하였다. 시뮬레이션과 실험을 통해 MIMO 시스템 특성의 유도 결합된 초전도코일의 전류제어 특성을 검증하였다.

• Proceedings of the KIPE Conference
• /
• 2014.11a
• /
• pp.72-73
• /
• 2014

본 논문에서는 ITER 펄스전원계통의 무효전력보상기(Reactive Power Compensator)의 해석 및 검증에 대하여 기술하였다. ITER 펄스전원계통은 66kV에 흐르는 무효전력량을 250MVar이하로 제한하기 위하여 정지형 무효전력보상기(Static Var Compensator)의 대표적인 장치인 싸이리스터 제어 리액터(TCR)와 고조파 필터(HF)로 구성된 무효전력보상기(RPC)를 사용한다. RPC에 적용되어 여러 ITER 초전도 코일 전원장치에서 발생하는 무효전력의 크기를 예측하여 보상하는 무효전력 보상기법을 해석한다. 본 논문에서는 RPC의 무효전력 보상동작을 실제 제어기와 RTDS를 연동하여 실험하여 검증하였고, RPC의 유무에 따라서 66kV 계통의 무효전력 최대값이 120MVar에서 40MVar로 감소하는 것을 확인하였다.

• Proceedings of the Korea Institute of Applied Superconductivity and Cryogenics Conference
• /
• 2001.02a
• /
• pp.48-49
• /
• 2001

Cryogenic technology is one of the key technologies for fusion reactor equipped with superconducting coil for plasma confinement. The KSTAR(Korea Superconducting Tokamak Advanced Research)Project is in progress since 1996. Major parameters of the KSTAR tokamak are : major radius 1.8m, minor radius 0.5m, toroidal field 3.5 Tesla and plasma current 2MA with a strongly shaped plasma cross-section and double -null diverter. Considering practical engineering constraints, the KSTAR device is designed for a pulse length of 300 sec in up-graded operation mode but in the initial configuration would provide a pulse length of 20 sec provided by the poloidal coil system in base-line operation mode. The cryogenic system is composed as follows : cold box, helium compressor system, distribution box, helium gas buffer tank, helium gas purifying system, gas recovery system, liquid helium storage dewar, current lead box, current bus line and liquid nitrogen storage tank.