• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 2005년도 ICCAS
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• pp.2331-2336
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• 2005

This paper proposes a new haptic device using a parallel mechanism with gimbal type actuators. This device has three legs actuated by 2-DOF gimbal mechanisms, which make the device simple and light by fixing all the actuators to the base. Three extra sensors are placed at passive joints to obtain a unique solution of the forward kinematics problem. The proposed haptic device is developed for an operator to use it on a desktop in due consideration of the size of an average Korean. The proposed haptic device has a small workspace for on operator to use it on a desktop and more sensitivity than a serial type haptic device. Therefore, the motors of the proposed haptic device are fixed at the base plate so that the proposed haptic device has a better dynamic bandwidth due to a low moving inertia. With this conceptual design, optimization of the design parameters is carried out. The objective function is defined by the fuzzy minimum of the global design indices, global force/moment isotropy index, global force/moment payload index, and workspace. Each global index is calculated by a SVD (singular value decomposition) of the force and moment parts of the jacobian matrix. Division of the jacobian matrix assures a consistency of the units in the matrix. Due to the nonlinearity of this objective function, Genetic algorithms are adopted for a global optimization.

• Nuclear Engineering and Technology
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• 제45권7호
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• pp.839-846
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• 2013

This paper describes a finite element model of the microstructure of dispersion type nuclear fuels, which can be used to determine the effective thermal conductivity of the fuels during irradiation. The model simulates a representative region of the fuel as a prism shaped unit cell made of brick elements. The elements within the unit cell are assigned material properties of either the fuel or the matrix depending on position, in such a way as to represent randomly distributed fuel particles with a size distribution similar to that of the as manufactured fuel. By applying an appropriate heat flux across the unit cell it is possible to determine the effective thermal conductivity of the unit cell as a function of the volume fraction of the fuel particles. The presence of a fuel/matrix interaction layer is simulated by the addition of a third set of material properties that are assigned to the finite elements that surround each fuel particle. In this way the effective thermal conductivity of the material may also be determined as a function of the volume fraction of the interaction layer. Work is on going to add fission gas bubbles in the fuel as a fourth phase to the model.

• Nuclear Engineering and Technology
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• 제49권3호
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• pp.576-580
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• 2017

A dynamic nanoindentation method was applied to study an Fe-18 at.% Gd alloy as a neutron-absorbing material prepared by vacuum arc-melting and cast in a mold. The Fe-18 at.% Gd cast alloy had a microstructure with matrix phases and an Fe-rich primary dendrite of $Fe_9Gd$. Rietveld refinement of the X-ray spectra showed that the Fe-18 at.% Gd cast alloy consisted of 35.84 at.% $Fe_3Gd$, 6.58 at.% $Fe_5Gd$, 16.22 at.% $Fe_9Gd$, 1.87 at.% $Fe_2Gd$, and 39.49 at.% ${\beta}-Fe_{17}Gd_2$. The average nanohardness of the primary dendrite phase and the matrix phases were 8.7 GPa and 9.3 GPa, respectively. The fatigue limit of the matrix phase was approximately 37% higher than that of the primary dendrite phase. The dynamic nanoindentation method is useful for identifying local phases and for analyzing local mechanical properties.

• 시스템엔지니어링학술지
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• 제10권1호
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• pp.17-32
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• 2014

The trade-off studies in the concept development stage to assess the relative goodness of alternative systems concepts for AE (architect engineering) design for the Barge Mounted SMR (BMSMR) is introduced. With respect to design margin, system performance, schedule and risk, the design selection is cond ucted using the following characteristics; barge mobility, system safety under the natural disaster (seismic), power output, interfacing with the other system, and the additional supporting functions as desalination. There are three findings that should be remedied; deficiencies in the assumed characteristics of the system being modeled, deficiencies in the test model, and excessively stringent system requirements. This study is performed using systems engineering approach with trade off matrix method. In order to execute this work, concept development stage is divided into three (3) phases as NA (needs analysis), CE (concept exploration), and CD (concept definition).

• 방사성폐기물학회지
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• 제17권4호
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• pp.363-373
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• 2019

Waste characterisation associated with nuclear site decommissioning relies on radiochemical analysis of a diverse range of sample types, requiring extensive validation of analytical techniques using matrix-matched materials. The absence of relevant reference materials has hindered robust method development and validation. The paper discusses how method validation in support of nuclear waste characterisation can be achieved without using reference materials. The key stages in an analytical procedure are evaluated and a multi-stage approach is proposed with the ultimate aim of determining an operational envelope for an analytical procedure.

• IMMUNE NETWORK
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• 제4권2호
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• pp.116-122
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• 2004

Background: LIGHT (TNFSF14) is a member of tumor necrosis factor superfamily and is the ligand for TR2 (TNFRSF14/HVEM). LIGHT is known to have proinflammatory roles in atherosclerosis. Methods: To find out the expression pattern of LIGHT in atherosclerotic plaques, immunohistochemical analysis was performed on human carotid atherosclerotic plaque specimens. LIGHT induced atherogenic events using human monocytic cell line THP-1 were also investigated. Results: Immunohistochemical analysis revealed expression of LIGHT and TR2 in foam cell rich regions in the atherosclerotic plaques. Double immunohistochemical analysis further confirmed the expression of LIGHT in foam cells. Stimulation of THP-1 cells, which express TR2, with either recombinant LIGHT or immobilized anti-TR2 monoclonal antibody induced interleukin-8 and matrix metalloproteinase(MMP)-9. Electrophoretic mobility shift assay demonstrated that LIGHT induces nuclear localization of transcription factor, nuclear factor $(NF)-{\kappa}B$. LIGHT induced activation of MMP-9 is mediated by $NF-{\kappa}B$, since treatment of THP-1 cells with the $NF-{\kappa}B$ inhibitor PDTC (pyrrolidine dithiocarbamate) completely blocked the activation of MMP-9. Conclusion: These data indicate that LIGHT is expressed in foam cells in atherosclerotic plaques and is involved in atherogenesis through activation of pro-atherogenic cytokine IL-8 and destabilization of plaque by inducing matrix degrading enzyme.

• Nuclear Engineering and Technology
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• 제45권7호
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• pp.859-870
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• 2013

The paper summarizes the irradiation test and post-irradiation examination (PIE) data for the U-Mo low-enriched fuel that was irradiated in the MIR reactor under the RERTR Program. The PIE data were analyzed for both full-size fuel rods and mini-rods with atomized powder dispersed in Al matrix as well as with additions of 2%, 5% and 13% of silicon in the matrix and ZrN protective coating on the fuel particles. The full-size fuel rods were irradiated up to an average burnup of ${\sim}60%^{235}U$; the mini-rods were irradiated to an average burnup of ${\sim}85%^{235}U$. The presented data show a significant increase of the void fraction in the U-Mo alloy as the U-235 burnup rises from ~ 40% up to ~ 85%. The effect of irradiation test conditions and U-235 burnup were analyzed with regard to the formation of an interaction layer between the matrix and fuel particles as well as generation of porosity in the U-Mo alloy. Shown here are changes in distribution of U fission products as the U-235 burnup increases from ~ 40% up to ~ 85%.

• Nuclear Engineering and Technology
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• 제54권9호
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• pp.3459-3469
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• 2022

Matrix composites of n-WO₃/n-Bi₂O₃/PVA with different loadings of n-WO₃/n-Bi₂O₃ mixtures (0-15 wt%) and starch (0 and 3 wt%) were fabricated by using melt-mixing method. The X-ray attenuation capability were evaluated based on mass attenuation coefficient (μ/⍴) using a general diagnostic X-ray machine at 40-100 kVp. The effect of starch addition on the dispersion of the fillers in the PVA matrix were observed by using FESEM through morphological analysis. The fabricated samples have shrunken and caused their thickness to be decreased (0.35 mm-0.55 mm) after the drying process even though fixed thickness (2.0 mm) was set initially. The density and HVL values of the samples with 3 wt% starch was seen lower than samples without starch (0 wt%), however the former have provided improvement in filler dispersion and better X-ray attenuation capability compared to the latter. As conclusion, the matrix composite of n-WO₃/n-Bi₂O₃/PVA with 15 wt% of n-Bi₂O₃, 8 wt% of n-WO₃ and 3 wt% starch can be selected as the best promising candidate for X-ray shielding materials.

• Nuclear Engineering and Technology
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• 제54권4호
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• pp.1161-1166
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• 2022

Green pitch coke with an average particle size of 2 mm was adopted as densifier and added to the raw materials of conventional A3-3 matrix graphite (MG) to prepare modified A3-3 matrix graphite (MMG) by the quasi-isostatic molding method. The structure, mechanical and thermal properties were assessed. Compared with MG, MMG had a more compact structure, and exhibited improved properties of higher mechanical strength, higher thermal conductivity and better molten salt barrier performance. Notably, under the same infiltration pressure of 5 atm, the fluoride salt occupation of MMG was only 0.26 wt%, whereas it was 15.82 wt% for MG. The densification effect of green pitch coke endowed MMG with improved properties for potential use in the spherical fuel elements of molten salt reactor.

• 핵의학기술
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• 제14권1호
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• pp.94-100
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• 2010

$^{99m}Tc$-DTPA를 이용한 사구체 여과율(Glomerular Filtration Rate, GFR) 측정은 간편한 방법으로 신장의 기능평가를 할 수 있는 장점이 있다. GFR 값은 순 주사기 계수, 신장 깊이, 교정 신장 계수, 영상획득 시간, 감마카메라의 특성 등 여러 원인에 의해 그 결과가 달라질 수 있다. 본 연구에서는 $^{99m}Tc$-DTPA를 이용한 GFR 측정에서 행렬크기(matrix size)와 주사 전 방사능 양의 변화가 계수 값에 미치는 영향을 알아보고자 하였다. 영상 획득에 사용된 장비는 GE사의 Infinia이며 확대계수(zoom factor)는 1.0으로 하여 저에너지 범용성 콜리메이터를 사용하였다. 촬영조건으로 행렬 크기(matrix size)는 $64{\times}64$, $128{\times}128$, $256{\times}256$으로 변화를 주었고, 주사 전 방사능 양은 $^{99m}Tc$-DTPA를 222 (6), 296 (8), 370 (10), 444 (12), 518 MBq (14 mCi)로 각각 74 MBq (2 mCi)단위로 증가시켜 각각의 행렬 크기에 따라 계수치를 얻었다. 주사기는 검출기로부터 30 cm 거리를 두고 5, 10, 20, 30, 40, 50, 60초까지 영상을 얻은 후 그 계수치를 비교하였다. 행렬 크기와 주사 전 방사능 양의 변화로 얻은 계수치를 실제 GFR 공식에 적용하였다. 행렬 크기 $64{\times}64$에서의 단위시간 당 계수치는 26.8, 34.5, 41.5, 49.1, 55.3 kcps, $128{\times}128$는 25.3, 33.4, 41.0, 48.4, 54.3kcps, $256{\times}256$의 경우는 25.5, 33.7, 40.8, 48.1, 54.7 kcps로 나타났다. 5초 동안 얻은 총 계수치는 $64{\times}64$에서 134, 172, 208, 245, 276 kcounts, $128{\times}128$는 127, 172, 205, 242, 271 kcounts, $256{\times}256$의 경우에는 137, 168, 204, 240, 273 kcounts로 나타났다. 그리고 60초 동안 얻은 총 계수치는 $64{\times}64$에서 1,503, 1,866, 2,093, 2,280, 2,321 kcounts, $128{\times}128$는 1,511, 1,994, 2,453, 2,890, 3,244 kcounts, $256{\times}256$의 경우에는 1,524, 2,011, 2,439, 2,869, 3,268 kcounts로 각각 나타났다. 총 계수치의 백분율 차이(% Difference)에 있어 $64{\times}64$는 최소 0%에서 최대 30.02%의 차이를 보였으며, $128{\times}128$와 $256{\times}256$은 각각 최소 0%에서 최대 0.60와 0.69%의 차이를 보였다. 행렬크기 $64{\times}64$의 계수 값에서 GFR 값은 주사 전 방사능 양이 222 MBq (6 mCi)에서 20초와 60초에서 0.37과 6.77%, 518 MBq (14 mCi)에서 20초와 60초에서 0.18과 42.89%로 얻었다. 그러나 $128{\times}128$와 $256{\times}256$에서는 0.60과 0.63%로 각각 나타났다. 행렬크기의 변화에서 $128{\times}128$과 $256{\times}256$은 주사 전 방사능 양과 계수 시간 변화에 따라 계수치 백분율과 GFR 값에 큰 변화를 보이지 않았다. 그러나 행렬크기가 $64{\times}64$에서는 주사 전 계수치가 1,500 kcounts를 초과할 때, 222 MBq (6mCi)에서는 50초와 518 MBq (14 mCi)에서는 30초 이상에서 주사 전 방사능 양과 시간의 변화에 따라 과잉계측이 서로 다르게 나타났으며, GFR 값에서는 더 큰 차이의 변화를 보였다. 따라서 $^{99m}Tc$-DTPA GFR 검사에서 주사 전 선량계측 시간에 따른 방사능 정량분석 검사에서는 행렬 크기, 주입 방사능 양, 그리고 획득시간 간의 변화 값을 정확히 알고 있어야 검사 결과에 대한 신뢰성을 확보 할 수 있을 것이다.