• 한국표면공학회지
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• 제50권3호
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• pp.183-191
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• 2017

In this study, surface morphology and mechanical property of TiN and DLC coated pedicle screw have been investigated by field-emission scanning electron microscopy, energy dispersive X-ray spectroscopy, X-ray diffraction, vickers hardness test, axial gripping, and axial torsional gripping capacity test. From the EDS and XRD results, the composition and crystal structure of TiN and DLC coated surface were verified. The hardness value was increased by TIN and DLC coating, and the DLC coating surface has the highest value. The gripping capacity also showed higher value for TiN and DLC coated specimen than that of non-coated (Ti alloy) surface. The surface morphology of gripping tested specimen showed rougher scratched surface from Ti alloy than TiN and DLC coated layer.

• 한국발생생물학회지:발생과생식
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• 제15권3호
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• pp.239-247
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• 2011

Spermatogenesis and taxonomic values of mature sperm morphology of in male Septifer (Mytilisepta) virgatus were investigated by transmission electron microscope observations. The morphologies of the sperm nucleus and the acrosome of this species are the cylinder shape and cone shape, respectively. Spermatozoa are approximately 45-50 ${\mu}m$ in length including a sperm nucleus (about 1.26 ${\mu}m$ long), an acrosome (about 0.99 ${\mu}m$ long), and tail flagellum (about 45-47 ${\mu}m$). Several electron-dense proacrosomal vesicles become later the definitive acrosomal vesicle by the fusion of several Golgi-derived vesicles. The acrosome of this species has two regions of differing electron density: there is a thin, outer electron-dense opaque region (part) at the anterior end, behind which is a thicker, more electron-lucent region (part). In genus Septifer in Mytilidae, an axial rod does not find and also a mid-central line hole does not appear in the sperm nucleus. However, in genus Mytilus in Mytilidae, in subclass Pteriomorphia, an axial rod and a mid-central line hole appeared in the sperm nucleus. These morphological differences of the acrosome and sperm nucleus between the genuses Septifer and Mytilus can be used for phylogenetic and taxonomic analyses as a taxonomic key or a significant tool. The number of mitochondria in the midpiece of the sperm of this species are five, as seen in subclass Pteriomorphia.

• Nuclear Engineering and Technology
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• 제31권4호
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• pp.391-400
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• 1999

A conceptual core design of the 1,300MWe KNGR (Korean Next Generation Reactor) without using soluble boron for reactivity control was developed to determine whether it is technically feasible to implement SBF (Soluble Boron Free) operation. Based on the borated KNGR core design, the fuel assembly and control rod configuration were modified for extensive use of burnable poison rods and control rods. A new fuel rod, in which Pu-238 had been substituted for a small amount of U-238 in fuel composition, was introduced to assist the reactivity control by burnable poison rods. Since Pu-238 has a considerably large thermal neutron capture cross section, the new fuel assembly showed good reactivity suppression capability throughout the entire cycle turnup, especially at BOC (Beginning of Cycle). Moreover, relatively uniform control of power distribution was possible since the new fuel assemblies were loaded throughout the core. In this study, core excess reactivity was limited to 2.0 %$\delta$$\rho$ for the minimal use of control rods. The analysis results of the SBF KNGR core showed that axial power distribution control can be achieved by using the simplest zoning scheme of the fuel assembly Furthermore, the sufficient shutdown margin and the stability against axial xenon oscillations were secured in this SBF core. It is, therefore, concluded that a SBF operation is technically feasible for a large sized LWR (Light Water Reactor).

• Nuclear Engineering and Technology
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• 제56권4호
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• pp.1125-1134
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• 2024

This paper presents a validation study of the subchannel analysis code SLTHEN used for the core thermal-hydraulic design of the Prototype Gen-IV sodium-cooled fast reactor (PGSFR). To assess the performance of the ENERGY model of SLTHEN, four liquid metal heating experiments conducted by ORNL, WARD, and KIT with hexagonal assemblies of wire-wrapped rod bundles were analyzed. These experiments were performed with 19-and 61-pin bundles and varying power distributions of axial and radial peaking factors up to 1.4 and 3.0, respectively. The coolant subchannel temperatures measured at different axial locations were compared with the SLTHEN predictions with the Novendstern, Chiu-Rohsenow-Todreas (CRT), and Cheng-Todreas (CT) correlations for flow split and mixing in wire-wrapped pin bundles. The results showed that the SLTHEN predicts the measured subchannel temperatures reasonably well with root-mean-square errors of ~10 % and maximum errors of ~20 %. It was also observed that the CRT and CT correlations consistently outperform the Novendstern correlation.

• Nuclear Engineering and Technology
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• 제17권2호
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• pp.105-115
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• 1985

정상상태하의 축방향높이 의존적 중성자속 버클링은 3차원적연소 이력자료로부터 도출된다. 과도상태에 있어서는 노내 및 노외중성자 측정기의 반응사이에 존재하는 선형적 관계로부터 물리적인 상관식을 개발하였다. 이 모델을 사용할 경우 제어봉의 위치가 크게 변하는 축방향 출력과도현상을 예측하는 1차원적 중성자 확산이론 프로그램의 신뢰도가 크게 향상된다.

• 한국지반공학회논문집
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• 제19권6호
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• pp.15-22
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• 2003

강관 내부 속채움한 현장타설말뚝에 대한 기존의 하중전이 측정에서는 강관의 변형률만 측정하고 콘크리트의 변형률은 강관과 동일하다고 가정하였으며, 시방서에 규정한 방법으로 구한 강관과 콘크리트의 탄성계수를 이용하여 말뚝 구성부재의 응력 및 축하중을 산정하였다. 그러나 강관의 변형률만 측정하여 강관과 콘크리트가 완전합성 거동하는 것으로 산정한 축하중은 실제 하중값과 상당한 차이를 보이고 있어 강관 내부 속채움한 현장타설말뚝의 거동을 정확히 분석할 수 없었다. 본 연구에서는 현장에서 제작한 콘크리트 공시체의 압축강도 시험을 통하여 탄성계수를 구하고 강재와 콘크리트의 변형률을 각각 측정할 수 있는 변형봉 센서를 이용하여 새로운 말뚝축하중 측정 방법을 제안하였다. 변형봉 센서를 사용하여 말뚝축하중을 산정할 경우 콘크리트의 탄성계수는 현장에서 제작한 콘크리트 공시체의 압축강도 시험에서 구하였으며, (0.2-0.6)$f_{ck}$의 응력 범위에 해당하는 평균접선기울기를 탄성계수로 사용하였다. 세 개의 현장타설말뚝에 대해 수행된 하중전이 측정 실험 결과를 이용하여 현장 적용성을 확인하였다. 변형봉 센서의 적용성은 대구경 현장타설말뚝에 대한 축하중 분포도를 통하여 확인하였는데, 말뚝머리에서 계산된 하중은 강관 내부속채움한 현장타설말뚝의 경우 실제작용하중에 비하여 -11∼-16% 오차를 나타내었으며, 현장타설 철근콘크리트말뚝의 경우 3.4% 오차를 나타내었다.

• 한국공간구조학회논문집
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• 제2권3호
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• pp.81-92
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• 2002

The objective of this paper is to help to make decision of the appropriate structural types in long span structured building due to range of span. For the intention, based on 7 forces of structural element, it is analized the relationships among 6 configurations of structural element(d/1), 25 structural types, 4 materials, and span-length known with 186 sample from 1850 to 1996. 1) bending forces: $club(1/100{\sim}1/10),\;plate(1/100{\sim}1/10),\;rahmen(steel,\;10{\sim}24m)\;simple\;beam(PC,\;10{\sim}35m)$ 2) shearing forces: $shell(1/100{\sim}1/1000)\;hyperbolic\;paraboloids(RC,25{\sim}97m)$ 3) shearing+bending forces: plate, folded $plate(RC21{\sim}59m)$ 4) compression axial forces: club, $arch(RC,\;32{\sim}65m)$ 5) compression+tension forces: shell, braced dome $shell(RC,\;40{\sim}201m),\;vault\;shell(RC,\;16{\sim}103m)$ 6) compression+tension axial forces: $rod(1/1000{\sim}1/100)$, cable(below 1/1000)+rod, coble+rod+membrane(below 1/1000), planar $truss(steel,\;31{\sim}134m),\;arch\;truss(31{\sim}135m),\;horizontal\;spaceframe(29{\sim}10\;8m),\;portal\;frame(39{\sim}55m),\;domical\;space\;truss(44{\sim}222m),\;framed\;\;membrane(45{\sim}110m),\;hybrid\;\;membrane\;(42{\sim}256m)$ 7) tension forces: cable, membrane, $suspension(60{\sim}150m),\;cable\;\;beam(40{\sim}130m),\;tensile\;membrane(42{\sim}136m),\;cable\;-slayed(25{\sim}90m),\;suspension\;membrane(24{\sim}97m),\;single\;layer\;pneumatic\;structure(45{\sim}231m),\;double\;layer\;pneumatic\;structures(30{\sim}44m)$

• Nuclear Engineering and Technology
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• 제28권2호
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• pp.162-174
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• 1996

서로 다른 지지격자들이 인접한 6$\times$6 핵연료 봉다발부수로내에서 국부 수력특성인자들을 레이저 유속 측정 장치인 LDV(Laser Doppler Velocimeter)를 이용하여 측정하였다. 6$\times$6 봉다발은 서로 다른 지지격자를 가진 3$\times$6 봉다발이 서로 인접하여 이룬 형상이다. 본 연구에서는 다른 형상과 다른 수력저항을 갖는 지지격자간들의 열수력적 상호작용을 규명하는데 그 목적이 있다. LDV를 이용하여 축방향 및 횡방향 속도, 난류강도 등의 측정 인자들을 측정하였다. 또한 압력강하를 측정하여 지지격자의 손실계수와 봉다발의 마찰계수를 구하였다. 수력실험결과에 근거하여 지지격자에 기인된 열혼합현상에 관한 것을 연구하였다. DNB의 정성적인 기준이라고 할 수 있는 swirl인자를 정의하고 횡방향속도 실험인자로부터 구하였다.

• 대한기계학회논문집B
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• 제41권1호
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• pp.53-62
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• 2017

이중냉각 환형핵연료 집합체를 위한 비틀림 혼합날개 지지격자의 강제대류열전달 성능을 실험적으로 평가하였다. 비틀림 혼합날개 지지격자는 부수로 간 혼합뿐 아니라 부수로 내 혼합을 동시에 증대시킬 수 있도록 설계되었다. 실험을 위한 이중냉각 환형핵연료 모의 집합체로, 봉 중심 간 거리와 봉 외경의 비가 1.08인 봉 간격이 좁은 $4{\times}4$ 정사각 배열의 봉다발을 준비하였다. 실험은 봉다발 유동의 축방향 평균속도가 1.5 m/s, 열유속은 $26kW/m^2$인 조건에서 수행하였다. 원주방향 온도 분포의 경우, 지지격자 상류에서는 부수로 중심 벽면에서, 하류에서는 비틀림 혼합날개 끝이 향하는 벽면에서 온도가 가장 낮게 나타났다. 축방향 온도 분포의 경우, 지지격자 하류 근처에서 온도가 급격하게 감소하는 것으로 측정되었고, 비틀림 혼합날개에 의해 누셀트 수는 최대 56 % 증대되는 것으로 나타났다. 본 실험결과를 토대로 봉 간격이 좁은 이중냉각 환형핵연료 집합체에서 비틀림 혼합날개 지지격자에 의해 강제대류열 전달 성능이 효과적으로 증대될 수 있음을 확인하였다.

• Nuclear Engineering and Technology
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• 제50권1호
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• pp.97-106
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• 2018

Improved load-following capability is one of the most important technical tasks of a pressurized water reactor. Controlling the nuclear reactor core during load-following operation leads to some difficulties. These difficulties mainly arise from nuclear reactor core limitations in local power peaking: the core is subjected to sharp and large variation of local power density during transients. Axial offset (AO) is the parameter usually used to represent the core power peaking. One of the important local power peaking components in nuclear reactors is axial power peaking, which continuously changes. The main challenge of nuclear reactor control during load-following operation is to maintain the AO within acceptable limits, at a certain reference target value. This article proposes a new robust approach to AO control of pressurized water reactors during load-following operation. This method uses robust feedback-linearization control based on the multipoint kinetics reactor model (neutronic and thermal-hydraulic). In this model, the reactor core is divided into four nodes along the reactor axis. Simulation results show that this method improves the reactor load-following capability in the presence of parameter uncertainty and disturbances and can use optimum control rod groups to maneuver with variable overlapping.