• 대한환경공학회지
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• 제39권8호
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• pp.449-455
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• 2017

기준공정과 개선대상공정 간의 투입물(Input, Material and energy), 배출물(Output, Product, Co-product), 환경오염물(Environmental emission) 데이터를 수집하고 공정 성과를 분석하였다. 이를 통해 환경적으로 주요한 투입물과 환경오염물을 파악하였다. 제조공정의 투입물과 환경오염물 간의 상관관계 분석을 통해 각 환경오염물에 대한 기여도가 큰 투입물을 파악하였다. 주요 환경오염물 처리 시, 경제적 최적화를 통한 종말처리공정 조합을 선형 프로그래밍 기법을 사용하여 규명하였다. 사례 연구로는 동일한 형태의 시멘트를 생산하는 EU와 국내 시멘트 제조공정을 선정하였다. 국내 시멘트 제조공정에서는 석탄이 주요 투입물로, 먼지, $SO_x$가 주요 환경오염물로 파악되었다. 제조공정의 투입물과 환경오염물 간의 다중회귀분석결과 석탄>원자재>석고 순으로 $CO_2$발생량에 기여도가 큰 것으로 나타났다. $SO_x$발생량의 경우 석탄의 기여도가 가장 컸으며, Dust 발생량의 경우 석고>원자재 순으로 기여도가 큰 것으로 나타났다. Dust 종말처리공정 최적화에서 전기집진기술 100%, 섬유필터기술 2.4% 조합이 최적이었다. $SO_x$종말처리공정 최적화에서는 건식첨가공정기술 100% 습식세정기술 25.88% 조합이 최적이었다. 이 연구의 특징은 제조공정에서 문제가 되는 주요 투입물과 환경오염물을 파악하는 방법을 제시하였다는 점이다. 또한, 기술적 경제적으로 최적의 조합인 종말처리공정 선정 방법을 제시하였다는 점이다.

• 소음진동
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• 제9권2호
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• pp.285-294
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• 1999

Transient analysis for compressible fluid flow has been performed experimentally and analytically to study the dynamic characteristics of the end volume transmission lines following a sudden pressure change a its entrance. The numerical method was developed based on the method of characteristics. The sudden pressure at its entrance was generated by rupture of diaphragm in a shock tube. The sudden pressure was used to obtain the response, as input signal for the numerical analysis. The response to the sudden pressure at the end volume was measured using a pressure transducer. The experimental result shows good agreements with the numerical result. The effects of tube length, its diameter and end volume magnitude are evaluated on the responses of the pressure and on the damping factor. It is found that the viscous damping effects on the response through the transmission pipeline becomes larger with increasing pi;eline length and decreasing diameter of the pipe and the fluid-elastic stiffness decreases with increasing the terminal volume. The numerical approach presented in this paper can be very useful in designing the instrument and control system.

• 한국정밀공학회지
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• 제14권8호
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• pp.29-39
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• 1997

The clamp, as the structure which is used for supporting the pipe in the atomic power plant, is produced with a certain degree of anticlastic curvature in the current manufacturing process. In this study, the structural analysis of the clamp and the pipe was performed using ABAQUS. And the finite element modelling for the analysis was made by an HyperMesh. The contact forces which are transferred between the clamp and the pipe for the external force are changed according to the binding force of bolts and keeps the clamp tightly and protects the slipping between the clamp and the pipe. The clamps with the anticlastic curvature and with the flat curvature are considered in order to invest the anticlastic effect. In this study, another case is suggested. The present case does not have the stiffness ring on the end of the clamp but the suggested case has the ring. For the present case, the results showed that the equivalent stress is higher in the anticlastic curvature case than in the flat curvature case and the equivalent stresses on the pipe are almost the same as the binding force increses. For the suggested case, the result showed that the equivalent stress in the anticlastic curvature case decreases until some binding force and increases as the binding forces increase and is lower in some range than in the flat curvature case. From this study, the clamp with the anticlastic curvature in the suggested method is better than the clamp with the flat curvature and the optimal binding force are given.

• Structural Engineering and Mechanics
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• 제64권5호
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• pp.671-681
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• 2017

This study investigates the structural performance of 3D steel pipe rack suspended scaffolding systems. For the purpose, a standard full scale 3D steel pipe rack suspended scaffolding system considering two frames, two plane trusses, purlins and wooden floor is constructed in the laboratory. A developed load transmission system was placed in these experimental systems to distribute single loads to the center of a specific area in a step-by-step manner using a load jack. After each load increment, the displacements are measured by means of linear variable differential transducers placed in several critical points of the system. The tests are repeated for five different system conditions to determine the structural performance. The means of system conditions is the numbers of the tie bars which are used to connect plane trusses under level. Finite elements models of the 3D steel pipe rack suspended scaffolding systems considering different systems conditions are constituted using SAP2000 software to support the experimental tests and to use the models in future studies. Each of models including load transmission platform is analyzed under a single loading and the displacements are obtained. In addition, to calibrate the numerical models some uncertain parameters such as elasticity modulus of wooden floor and connection rigidity of purlins to plane trusses are assessed experimentally. The results of this work demonstrate that when increasing numbers of tie bars the displacement values are decreased. Also the results obtained from developed numerical models have harmony with those of experimental. In addition, the scaffolding system with two tie bars at the beginning and at the end of the plane truss has the optimum structural performance compared the results obtained for other scaffolding system conditions.

• 한국공작기계학회논문집
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• 제11권6호
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• pp.75-82
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• 2002

Design for a quiet operation of fluid power system requires the understanding of noise and vibration characteristics of the system. It's not easy to analyze noise problem in hydraulic cylinder used in typical actuator Because they've got complex fluid dynamics. One of the fundamental problems associated with the hydraulic system is the pulsating flow in pipe lines, which can be tackled by the analysis under simplifying assumptions. The present study focuses on theoretic analysis and experimental study on the dynamics of laminar pulsating flow in a circular pipe. We analyze the propagation characteristics of the pressure pulse within a hydraulic pipe line taking into account the pulsating flow frequency variation. We also measure instantaneous pressure pulses within pipe line to identify the transfer functions. We conduct series of experiments to investigate the propagation characteristics of pressure pulse for various pressure of pulsating flow. The working fluid of the present study is ISO VG46 and the temperature ranges from 20 to $60^{\circ}$ with normal pressure at 4000kPa. The flow rate is measured by using an ultrasonic flow meter. Pressures at fixed upstream and downstream positions are measured concurrently. The electric signals of the pressure sensor are stored and analyzed using a system analyzer(PKE 983 series). The frequency is varied in the range of 10~500Hz. The Reynolds number is kept below 2,000. In the present study, boundary condition was varied by installing a surge tank and an orifice at the end of pipe. Experimental and theoretical results were compared each other under various boundary conditions.

• 한국지반신소재학회논문집
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• 제16권2호
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• pp.67-77
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• 2017

본 연구에서는 콘 장비를 강관말뚝 중공에 설치함에 따른 말뚝의 거동을 분석하기 위해 축소 모형실험을 진행하였다. 콘 장비를 항타하여 설치 할 경우 먼저 강관 내부에 유입되는 관내토의 높이를 수치상으로 확인 할 수 있으며, 이를 통해 플러깅을 예측하여 플러깅에 따른 말뚝의 거동을 분석 할 수 있다. 또한 물리적인 항타 에너지로 지반의 강성과 강도를 증가 시켜 지지력을 상승 시킬 것으로 기대된다. 강사 장치를 이용하여 상대밀도 90%의 지반을 조성하고 거칠기가 다른 두 강관말뚝을 항타높이를 200mm와 500mm로 나누어 근입깊이 600mm까지 설치한다. 그리고 콘 장비의 유무에 따라 총 8가지 케이스를 나누어 말뚝의 지지력을 분석하였다. 말뚝의 항타높이, 말뚝의 거칠기, 콘 장비의 유무에 따른 세 가지 변수 중 항타높이가 약 70%로 지지력에 미치는 영향이 가장 컸으며 다음으로 콘 장비의 유무가 약 40%, 말뚝의 거칠기가 약 21%로 나타났다.

• Nuclear Engineering and Technology
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• 제54권6호
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• pp.2094-2106
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• 2022

The solid-state core of a heat pipe cooled reactor operates at high temperatures over 1000 K with thermal and irradiation-induced expansion during burnup. The expansion changes the gap thickness between the solid components and the material properties, and may even cause the gap closure, which then significantly influences the thermal and mechanical characteristics of the reactor core. This study developed an irradiation behavior model for HPRTRAN, a heat pipe reactor system analysis code, to introduce the irradiation effects such as swelling and creep. The megawatt heat pipe reactor MegaPower was chosen as an application case. The coupled irradiation-thermal-mechanical model was developed to simulate the irradiation effects on the heat transfer and stresses of the whole reactor core. The results show that the irradiation deformation effect is significant, with the irradiation-induced strains up to 2.82% for fuel and 0.30% for monolith at the end of the reactor lifetime. The peak temperatures during the lifetime are 1027:3 K for the fuel and 956:2 K for monolith. The gap closure enhances the heat transfer but caused high stresses exceeding the yield strength in the monolith.

• Nuclear Engineering and Technology
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• 제55권1호
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• pp.364-372
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• 2023

The space reactor is the primary energy supply for future space vehicles and space stations. The radiator is one of the essential parts of a space reactor. Therefore, the research on radiators can improve the heat dissipation power, reduce the quality of radiators, and make the space reactor smaller. Based on MOOSE multi-physics numerical calculation platform, a simulation program for the combination of heat pipe and fin at the end of heat pipe radiator is developed. It is verified that the calculation result of this program is accurate and the calculation speed is fast. Analyze the heat transfer characteristics of the combination with heat pipe and fin, and obtain its internal temperature field. Based on the calculation results, the influence of structural parameters on the heat dissipation power is analyzed. The results show that when the fin width is 0.25 m, fin thickness is 0.002 m, condensing section length is 0.5425 m and heat pipe radius is 0.014 m, the power-mass ratio is the highest. When the temperature is 700K-900K, the heat dissipation power increases 41.12% for every 100K increase in the operating temperature. Smaller fin width and thinner fin thickness can improve the power-mass ratio and reduce the radiator quality.

• 한국지반공학회논문집
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• 제21권5호
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• pp.33-43
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• 2005

본 연구는 단부의 경계조건에 따른 매설관의 동적응답을 규명하기 위해 축방향 및 축직각방향에 대해서 자유진동과 강제진동 해석을 수행하였다. 각 경계조건에서의 모드형상을 결정한 후 고유진동수를 구하고, 이들을 이용하여 강제 진동시 발생하는 매설관의 축방향에 대해 변위, 변형률 산정식과 축직각방향에 대한 변위, 휨변형률 산정식을 유도하였다. 또한 가능한 모든 단부 경계조건의 매설관에 대해 최대응력이 발생하는 위치와 크기를 산정하였으며, 매설관의 동적거동에 영향을 가장 많이 발생시킬 수 있는 공진현상을 나타내는 모드수를 예측할 수 있는 식을 제안하였고 관 단부 경계조건이 매설관의 동적응답에 미치는 영향에 대한 규명과 관의 동적응답에 영향을 주는 매개변수들의 영향에 대해 규명하였다.

• 대한기계학회논문집A
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• 제32권8호
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• pp.668-677
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• 2008

In nuclear power plants, ferritic low alloy steel nozzle was connected with austenitic stainless steel piping system through alloy 82/182 butt weld. Accurate estimation of residual stress for weldment is important in the sense that alloy 82/182 is susceptible to stress corrosion cracking. There are many results which predict residual stress distribution for alloy 82/182 weld between nozzle and pipe. However, nozzle and piping system usually connected through safe end which has short length. In this paper, residual stress distribution for pressurizer nozzle of Kori nuclear power plant was predicted using FE analysis, which consideded safe end. As a result, existing residual stress profile was redistributed and residual stress of inner surface was decreased specially. It means that safe end should be considered to reduce conservatism when estimating the piping system.