• 한국산업융합학회 논문집
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• 제25권4_2호
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• pp.611-619
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• 2022

In this study, the seismic performance of low - rise piloti buildings with concentric core (shear wall) position is analysed and reviewed based on KDS 41. The prototype is selected among the constructed low - rise piloti buildings with concentric core designed based on KBC 2005 which was used for many low - rise piloti buildings construction. The seismic performance of the building shows plastic behavior in X-direction and elastic behavior in Y-direction. The inter-story drift is lager than that of concentric core case and is under the maximum allowed drift ratio. The displacement ratio of first story is much lager the that of upper stories, and the frame structure in the first story is evaluated as vulnerable to lateral force. Therefore, low - rise piloti buildings with concentric core need the diminishment of lateral displacement and reinforcement of lateral resistance capacity in seismic design and seismic retrofit.

• Nuclear Engineering and Technology
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• 제56권3호
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• pp.922-932
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• 2024

This paper presents the design features and preliminary design analysis results of the Wielenga Innovation Static Salt Reactor (WISSR). The WISSR incorporates features that make it both flexible and inherently safe. It is based on innovative technology that controls a nuclear reactor by moving molten salt fuel into or out of the core. The reactor is a low-pressure, fast spectrum transuranic (TRU) burner reactor. Inherent shutdown is achieved by a large negative reactivity feedback of the liquid fuel and by the expansion of fuel out of the core. The core is made of concentric, thin annular fuel chambers containing molten fuel salt. A molten salt coolant passes between the concentric fuel chambers to cool the core. The core has both fixed and variable volume fuel chambers. Pressure, applied by helium gas to fuel reservoirs below the core, pushes fuel out of a reservoir and up into a set of variable volume chambers. A control system monitors the density and temperature of the fuel throughout the core. Using NaCl-(TRU,U)Cl₃ fuel and NaCl-KCl-MgCl₂ coolant, a road-transportable compact WISSR core design was developed at a power level of 1250 MWt. Preliminary neutronics and thermal-hydraulics analyses demonstrate the technical feasibility of WISSR.

• Journal of information and communication convergence engineering
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• 제14권3호
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• pp.163-170
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• 2016

Because of rapid technological advancements, increased data rate support has become the key criterion for future communication medium selection. Multimode optical fibers and multicore optical fibers are well matched to high data rate throughput requirements because of their tendency to support multiple modes through one core at a time, which results in higher data rates. Using the numerical mode solver OptiFiber, we have designed a concentric core fiber by investigating certain design parameters, namely core diameter (µm), wavelength (nm), and refractive index profile, and as a result, the number of channels, material losses, bending losses, polarization mode dispersion, and the effective nonlinear refractive index have been determined. Space division multiplexing is a promising future technology that uses few-mode fibers in parallel to form a multicore fiber. The experimental tests are conducted using the standard second window wavelength of 1,550 nm and simulated results are presented.

• 대한기계학회논문집B
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• 제23권5호
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• pp.587-592
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• 1999

The combined effects of radius ratio and roughness pitch ratio on the turbulent fluid flow characteristics of the fully developed flow in the annullar tubes with rib-roughened core walls were determined for Reynolds number ranging from 12,000 to 66,000. To understand the underlying physical phenomena responsible for friction factor enhancement, measurements of velocity profiles and zero shear stress and maximum velocity positions were combined to propose the friction factor correlation. Friction factors were found to be a function of the roughness pitch ratio and radius ratio.

• 전기학회논문지
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• 제67권6호
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• pp.702-707
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• 2018

In case of Lighting occurs in Domestic combined distribution line, normally the voltage for the neutral line increase dramatically. General connection for underground cable is bundled common earth type so the lightning over voltage increase at the concentric-neutral line is not big enough to give impact on cable sheath. But in case of Non bundled common earth type it is necessary to analyze the phenomena on cable sheath caused by lightening overvoltage. Especially pole and cable joint are the core factor to consider. In this paper concrete pole and cable joint were evaluated in case of Non bundled common earth type combined distribution Line. EMTP simulation model has been designed and several case study were made. Also several experimental test were made to verify the simulation result.

• PNF and Movement
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• 제22권2호
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• pp.233-242
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• 2024

Purpose: The aim of this study was to investigate the effects of different types of unstable loads on core and lower limb muscle activity during squatting. Methods: Nineteen subjects (all females) with resistance experience but no unstable resistance experience participated in the study. Subjects performed squats under three load conditions, and core and lower limb muscle activity was measured during eccentric and concentric contractions. Results: During the eccentric contraction, core and hip flexor activity was significantly higher with the aqua bag than with the barbell or resistance band, and for the quadriceps, the resistance band was significantly higher than the barbell. During the concentric contraction phase, core and hamstring muscle activity was significantly higher with the aqua bag than with the barbell and elastic band (p < 0.05). Conclusion: Squats with an aqua bag increase core and biceps brachii activation and can be recommended as a training method to improve trunk stability.

• 대한기계학회논문집B
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• 제26권11호
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• pp.1513-1520
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• 2002

Effect of Convex Surface Curvature on the Onset of Nucleate Boiling of Subcooled Fluid Flow in Vertical Concentric Annuli An experimental study has been carried out to investigate the effect of the transverse convex surface curvature of core tubes on heat transfer in concentric annular tubes. Water is used as the working fluid. Three annuli having a different radius of the inner cores, Ri=3.18mm, 6.35mm, and 12.70mm with a fixed ratio of Ri/Ro=0.5 are used over a range of the Reynolds number between about 40,000 and 80,000. The inner cores are made of smooth stainless steel tubes and heated electrically to provide constant heat fluxes throughout the whole length of each test section. Experimental result shows that heat flux values on the onset of nucleate boiling of the smaller inner diameter model is much higher than that of the larger size test model.

• 대한기계학회논문집
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• 제9권5호
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• pp.663-676
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• 1985

수평원통형의 복합유동층에서의 층류자연대류를 수치적으로 연구하였다. 외측의 동심원환이 내 의 발열유체로 형성된 원통형 핵을 둘러싸고, 그 사이에 두께가 유한하거나 두께를 무시할 수 있 는 간막이 벽이 존재한다. 유동특성과 열전달에 관한 매개변수적 고찰을 시행하거나 직경비, Prandt1수, 발열강도에 기준을 둔 Rayleigh수 등의 영향을 이해하게 되었다. 간막이 벽의 두께나 열전도의 효과도 제한된 범위 안에서 고려하였다.

• 한국지구과학회지
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• 제42권2호
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• pp.185-194
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• 2021

제주도 북서부인 애월 해안에는 평탄하게 흐른(판상) 용암류와 둥근 모양(원통)의 용암류가 관찰된다. 원통형 용암류의 치밀한 내부에는 동심원 구조와 방사상 절리가 발달한다. 구엄리 돌염전 주변의 판상 용암류 내부에는 상하부의 굵기가 다른 주상절리가 발달한다. 주상절리 상부는 다각형의 형태가 고르지 않으며 직경은 120-150 cm이다. 주상절리 하부는 육각형과 오각형으로 형태가 일정하고, 크기도 60 cm 내외이다. 원통형 로브는 크기와 형태에 따라 두 그룹으로 나눌 수 있다. 하나는 메가로브인데, 최대 직경이 30 m인 반원형이다. 또 하나는 원형의 로브로 직경이 10 m 이하이다. 원통형 용암류의 방사상 절리의 기둥 단면은 육각형과 오각형이며, 기둥의 직경은 중심에서 바깥쪽으로 증가하는데 바깥쪽 경계부에서는 80-120 cm 정도이다. 원통형 용암에서 관찰되는 동심원 구조는 4가지 요인이 복합된 것이다. 첫째는 원형의 균열로, 원통형 용암류 내에서 안쪽과 바깥쪽 사이의 온도차와 밀도차로 발생한 수축으로 생긴 틈새이다. 둘째는 방사상 절리의 마디층이 동심원을 이룬 것으로, 이 마디층은 방사상 절리와 동시에 만들어진 것이다. 셋째는 유동띠로서, 용암이 흐를 때 둥근 통로에 남긴 흔적이다. 네 번째는 용암에서 빠져나온 가스가 동굴에 형성된 기공 띠이다.

• Nuclear Engineering and Technology
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• 제51권5호
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• pp.1314-1321
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• 2019

In case of multiple failure scenario, such as LOCA with ECCS failure, the decay heat continues to raise the reactor core temperature, eventually leading to the core voiding. In such scenario the convective heat transfer becomes poor and the majority of the heat transfer from fuel bundle takes place by radiation mode. During this abnormal working condition, if the channel pressure is less than 1 MPa, the PT sags and come in contact with the CT. This results in high rate of heat transfer from contact location to moderator. The present paper aims to capture the temperature profile over a simulated nuclear channel during such scenario at a steady state temperature of $600^{\circ}C$ (Centre pin) at two different configurations of PT i.e. PT concentric with CT and PT contact with CT. The results showed that the bottom nodes of all the components (Fuel bundle, PT and CT) of the simulated channel was greatly influenced by the PT/CT contact. Moreover, higher temperature were observed at top nodes of the PT and outer pins of the fuel bundle. However, no significant variation in temperatures were obtained in fuel bundle and CT in concentric condition.