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KSTAR 진공용기 및 플라즈마 대향 부품에 대한 베이킹 해석
이강희(K. H. Lee),임기학(K. H. Im),허남일(N. I. Her),인상렬(S. R. In),조승연(S. Y. Cho) 한국진공학회(ASCT) 1999 Applied Science and Convergence Technology Vol.8 No.4(1)
KSTAR (Korea Superconducting Tokamak Advanced Research) 토카막 핵융합 실험장치의 진공용기는 불순물이 적은 깨끗한 플라즈마 발생을 위해 기저압력이 초고진공(10^6~10^(-7)Pa)이어야 하며 이의 실현을 위해 진공용기 내부의 불순물을 제거할 목적으로 진공용기는 250℃, 각종 플라즈마 대향 부품들은 350℃까지 베이킹 될 필요성이 있다. 본 논문에서는 계획된 베이킹 시나리오에 준하여 필요 입열율을 산출해보고 이를 근거로 적절한 베이킹 계획을 정한 후 KSTAR 질소가스 유동 베이킹 시스템에 필요한 가스의 시간에 따른 온도와 유량을 산출하였다. The base pressure of the vacuum vessel of KSTAR tokamak is to be a ultra high vacuum, 10^6~10^(-7)Pa, to produce a clean plasma with low impurity concentrations. For this purpose, vessel and plasma facing components need to be baked up to 250℃, 350℃ respectively to remove impurities from the plasma-material interaction surfaces. Here the required heating power to be supplied for baking has been calculated according to pre-assumed different temperature profiles (baking scenario) and proper baking plan for KSTAR tokamak has been proposed. Mass flow rate and temperature of nitrogen gas for baking has also been calculated.
이강희(K-H Lee),강흥석(H-S Kang),송기남(K-N Song),윤경호(K-H Yoon),최명환(M-H Choi) 대한기계학회 2004 대한기계학회 춘추학술대회 Vol.2004 No.4
Vibration characteristics of the FIV test loop for the Flow-Induced Vibration(FIV) study of a PWR partial(5x5) fuel assembly are investigated by the Finite Element(FE) analysis and the modal test. For the FE analysis, 3-D beam element is used for the pipes and the test section and mass element used for the valves and flanges. The 'U' restrainer stiffness determined by numerical simulation is used for the FE model. The result of the FE analysis is compared with that of the modal test. The higher mode similarity between the test and analysis is observed in a few low modes. After that, the mode similarity reduce as the mode goes high. It is concluded that the first to the third vibration modes are observed at the lower parts of the 6 inches restoring line, followed by a local mode at the test section, and the natural frequencies of the modes are 22.4 Hz, 26.0 Hz, 27.5 Hz and 31.4 Hz.
유한요소법에 의한 경수로용 핵연료집합체의 낙하충격 해석
윤경호(K-H Yoon),안창기(C-K An),이강희(K-H Lee),송기남(K-N Song) 대한기계학회 2005 대한기계학회 춘추학술대회 Vol.2005 No.11
The drop impact analysis of a fuel assembly for pressurized water reactor (PWR) power plant is executed by finite element analysis method. The used commercial FE codes are the ANSYS and LS-DYNA3D. The analysis results are compared with the previous experimental results. The impact force results differed from the analysis condition depending on how many fuel rods slipped down to the bottom nozzle. And the joint and connection parts between components of a fuel assembly are very important for determining the stiffness of it. The fuel assembly experienced an impact force of approximately 95.65kN when dropped from a height 25 ㎜ with the fuel rods off the bottom nozzle. The developed finite element model and analysis procedure will be useful tool for evaluating the stiffness and strength of a fuel assembly.
윤경호(K-H Yoon),이강희(K-H Lee),송기남(K-N Song) 대한기계학회 2006 대한기계학회 춘추학술대회 Vol.2006 No.3
The pendulum type impact test is established for evaluating the buckling behavior of a grid structure under the lateral impact load. This grid structure is composed several thin plates by laser welding. The test data acquired as initial impact angular, which were impact acceleration, force and duration time. These critical buckling strength are affected the configuration of grid structure. The cylindrical tube insertion case with fuel rod cell showed higher strength than that of the empty grid structure. And the thicker cylindrical tube insertion case with guide tube cell also represented a little higher value than that of the only fuel rod tube configuration case. Even though, the support condition of the grid structure was non-linear characteristic behavior due to friction force between two parts, these cylindrical tube cases expressed much higher than that of the only shell structure case. When the design criteria for the seismic and accident event will be raise in next generation fuel, it needs more robust design grid structure by shape optimization of the strap and joint connection method re-design.