• 한국소성가공학회:학술대회논문집
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• 한국소성가공학회 2004년도 춘계학술대회 논문집
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• pp.269-272
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• 2004

The present study used a diagrammatic analysis of 6 sigma quality control and Taguchi method for injection molding process of monitor back-cover, evaluated the influence on the cycle time with part design, mold design, molding process and standardization activity involving design & molding, adopted analysis of sensitivity and effective factors of the part design and molding process conditions for productivity, identified main design molding factors, as critical ones influencing on the quality and productivity, of which is summarized as design guidance. The main contribution factors for cycle time can be sequentially enumerated as follows; hot spot, part thickness, coolant inlet temperature, melt temperature cooling line layout, etc.. As a first step critical factors of the design process of current monitor housing were investigated. And the optimal and better critical factors found in the first step were applied to a new product proving our process was correct. Moldflow software was used for injection molding simulation, and Minitab software for the statistical analysis. Finally, the productivity was increased by about 33 percents for our specific case.

• Nuclear Engineering and Technology
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• 제52권7호
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• pp.1417-1428
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• 2020

The design of a nuclear reactor core requires basic thermal-hydraulic information concerning the heat transfer regime at which onset of nucleate boiling (ONB) will occur, the pressure drop and flow rate through the reactor core, the temperature and power distributions in the reactor core, the departure from nucleate boiling (DNB), the condition for onset of flow instability (OFI), in addition to, the critical velocity beyond which the fuel elements will collapse. These values depend on coolant velocity, fuel element geometry, inlet temperature, flow direction and water column above the top of the reactor core. Enough safety margins to ONB, DNB and OFI must-emphasized. A heat transfer package is used for calculating convection heat transfer coefficient in single phase turbulent, transition and laminar regimes. The main objective of this paper is to study the possibility of power upgrading of WWR-S research reactor from 2 to 10 MW_th. This study presents a one-dimensional mathematical model (axial direction) for steady-state thermal-hydraulic design and analysis of the upgraded WWR-S reactor in which two types of plate fuel elements are employed. FOR-CONV computer program is developed for the needs of the power upgrading of WWR-S reactor up to 10 MW_th.

• Nuclear Engineering and Technology
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• 제53권9호
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• pp.2803-2815
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• 2021

This paper addresses the uncertainty quantification and sensitivity analysis of a depleted light-water fuel assembly of the Turkey Point-3 benchmark. The uncertainty of the fuel assembly decay heat and isotopic densities is quantified with respect to three different groups of diverse parameters: nuclear data, assembly design, and reactor core operation. The uncertainty propagation is conducted using a two-step analysis code system comprising the lattice code STREAM, nodal code RAST-K, and spent nuclear fuel module SNF through the random sampling of microscopic cross-sections, fuel rod sizes, number densities, reactor core total power, and temperature distributions. Overall, the statistical analysis of the calculated samples demonstrates that the decay heat uncertainty decreases with the cooling time. The nuclear data and assembly design parameters are proven to be the largest contributors to the decay heat uncertainty, whereas the reactor core power and inlet coolant temperature have a minor effect. The majority of the decay heat uncertainties are delivered by a small number of isotopes such as ²⁴¹Am, ¹³⁷Ba, ²⁴⁴Cm, ²³⁸Pu, and ⁹⁰Y.

• Journal of Advanced Marine Engineering and Technology
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• 제10권2호
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• pp.156-164
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• 1986

In the case of boiling on high temperature wall, vapor film covers fully or parcially the surface. This phenomenon, film boiling or transition boiling, is very important in the surface heat treatment of metal, design of cryogenic heat exchanger and emergency cooling of nuclear reactor. Mainly supposed hydraulic-thermal accidents in nuclear reactor are LCCA (Loss of Coolant Accident) and PCM (Power-Cooling Mismatch). Recently, world-wide studies on reflooding of high temperature rod bundles after the occurrence of the above accidents focus attention on wall temperature history and required time in transient cooling process, wall superheat at rewet point, heat flux-wall superheat relationship beyond the transition boiling region, and two-phase flow state near the surface. It is considered that the further systematical study in this field will be in need in spite of the previous results in ref. (2), (3), (4). The paper is the study about the fast transient cooling process following the wall temperature excursion under the CHF (Critical Heat Flux) condition in a forced convective subcooled boiling system. The test section is a vertically arranged concentric annulus of 800 mm long and 10 mm hydraulic diameter. The inner tube, SUS 304 of 400 mm long, 8 mm I.D, and 7 mm O.D., is heated uniformly by the low voltage AC power. The wall temperature measurements were performed at the axial distance from the inlet of the heating tube, z=390 mm. 6 chromel- alumel thermocouples of 76 .mu.m were press fitted to the inner surface of the heating tube periphery. To investigate the heat transfer characteristics during the fast transient cooling process, the outer surface (fluid side) temperature and the surface heat flux are computed from the measured inner surface temperature history by means of a numerical method for inverse problems of transient heat conduction. Present cooling (boiling) curve is sufficiently compared with the previous results.

• 한국가스학회지
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• 제8권1호
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• pp.1-6
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• 2004

선박용 열교환기의 냉각수로 사용되고 있는 해수의 입구온도는 스팀터빈콘덴서의 경우 약 $25^{\circ}C$이고 출구온도는 약 $60^{\circ}C$이며, 오일쿨러의 경우 출구온도는 약 $40^{\circ}C$이다. 이러한 해수의 온도 변화는 열교환기 세관재의 부식특성에 크게 영향을 미친다. 그러므로 부식손상을 최소화하면서 열교환 효율을 최대로 유지할 수 있는 냉각용액의 온도설정은 매우 중요하다. 따라서 본 연구에서는 $3.5\%$ NaCl + $0.1\%\;NH_4OH$ 수용액의 유동하에서 선박용 열교환기 세관재로 사용되고 있는 Al-황동의 분극 및 응력부식균열 실험을 실시하여 분극특성, 응력부식균열거동 및 탈아연특성에 미치는 용액의 온도의 영향에 대하여 고찰하였다.

• 대한기계학회논문집B
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• 제41권11호
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• pp.735-742
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• 2017

본 연구에서는 PEM 연료전지 온도 센서의 고장을 감지 및 판별할 수 있는 모델 기반 센서 고장 감지 방법이 적용된다. 연료전지 차량이 작동하는 과정에서 스택 온도는 연료전지의 내구성에 영향을 미친다. 따라서 고장 진단 알고리즘이 고장 신호를 감지하는 것은 중요하다. 센서 고장 감지의 주요 목적은 연료전지 시스템의 안정적인 작동을 보장하여 고온과 저온으로부터 스택을 보호하는 것이다. 상태 공간에 기반한 패러티 방정식이 스택 온도와 냉각수 입구 온도와 같은 센서 고장을 감지하는데 적용되며, 잔차는 정상적인 온도 신호와 비교된다. 그리고 잔차는 현재의 센서 고장을 감지하는 다양한 고장 시나리오에 의해 평가된다. 결론적으로, 본 연구에서 설계된 고장 알고리즘이 고장 신호를 감지할 수 있다.

• 대한기계학회논문집B
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• 제36권12호
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• pp.1185-1192
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• 2012

차량용 연료전지는 내연기관보다 운전 온도가 낮아 냉각수의 온도를 낮게 관리해야 하며, 이러한 냉각수 온도는 대기와의 온도차가 내연기관보다 작아 고성능 방열판 및 열관리계가 요구된다. 이러한 차량용 연료전지 열 관리계는 특히 연료전지 운전 온도 및 스택 내 온도분포를 결정하는 중요한 구성품이다. 본 연구에서는 차량용 연료전지 열 관리계 모델을 Matlab/$Simulink^{(R)}$ 환경 하에 개발하였으며, 기본 설계에 적용이 가능하도록 방열판 상세 모델을 개발하고 열 관리계는 팬, 모터, 방열판 그리고 냉각수 펌프로 구성하였다. 팬과 펌프는 경험식을 이용해 모델을 개발하였으며 모터 동특성을 고려하였다. 두 구성품은 연료전지의 입구와 출구 온도를 추출해 정해진 지령을 수령하도록 제어 하였다. 본 연구에는 연료전지 차량에 적합한 방열기 설계를 위해 방열기 특성을 확인하고, 이를 연료전지 시스템과 통합운전하면서, 연료전지 운전제어에 적절한 지 확인하였다.

• Nuclear Engineering and Technology
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• 제54권3호
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• pp.842-848
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• 2022

Parametric studies of heat transfer and fluid flow are very important research of interest because the design and operation of fluid flow and heat transfer systems are guided by these parametric studies. The safety of the system operation and system optimization can be determined by decreasing or increasing particular fluid flow and heat transfer parameter while keeping other parameters constant. The parameters that can be varied in order to determine safe and optimized system include system pressure, mass flow rate, heat flux and coolant inlet temperature among other parameters. The fluid flow and heat transfer systems can also be enhanced by the presence of or without the presence of particular effects including gravity effect among others. The advanced Generation IV reactors to be deployed for large electricity production, have proven to be more thermally efficient (approximately 45% thermal efficiency) than the current light water reactors with a thermal efficiency of approximately 33 ℃. SCWR is one of the Generation IV reactors intended for electricity generation. High Performance Light Water Reactor (HPLWR) is a SCWR type which is under consideration in this study. One-eighth of a proposed fuel assembly design for HPLWR consisting of 7 fuel/rod bundles with 9 coolant sub-channels was the geometry considered in this study to examine the effects of system pressure and mass flow rate on wall and fluid temperatures. Gravity effect on wall and fluid temperatures were also examined on this one-eighth fuel assembly geometry. Computational Fluid Dynamics (CFD) code, STAR-CCM+, was used to obtain the results of the numerical simulations. Based on the parametric analysis carried out, sub-channel 4 performed better in terms of heat transfer because temperatures predicted in sub-channel 9 (corner subchannel) were higher than the ones obtained in sub-channel 4 (central sub-channel). The influence of system mass flow rate, pressure and gravity seem similar in both sub-channels 4 and 9 with temperature distributions higher in sub-channel 9 than in sub-channel 4. In most of the cases considered, temperature distributions (for both fluid and wall) obtained at 25 MPa are higher than those obtained at 23 MPa, temperature distributions obtained at 601.2 kg/h are higher than those obtained at 561.2 kg/h, and temperature distributions obtained without gravity effect are higher than those obtained with gravity effect. The results show that effects of system pressure, mass flowrate and gravity on fluid flow and heat transfer are significant and therefore parametric studies need to be performed to determine safe and optimum operating conditions of fluid flow and heat transfer systems.

• 한국자동차공학회논문집
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• 제21권6호
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• pp.81-91
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• 2013

A novel design process of a parallel multi-flow type air-cooled condenser of a dual-loop waste heat recovery system with Rankine steam cycles for improving the fuel efficiency of gasoline automobiles has been investigated focusing on reduction of the pressure drop inside the micro-tubes. The low temperature condenser plays a role to dissipate heat from the system by condensing the low temperature loop working fluid sufficiently. However, the refrigerant has low evaporation temperature enough to recover the waste from engine coolant of about $100^{\circ}C$ but has small saturation enthalpy so that excessive mass flow rate of the LT working fluid, e.g., over 150 g/s, causes enormously large pressure drop of the working fluid to maintain the heat dissipation performance of more than 20 kW. This paper has dealt with the scheme to design the low temperature condenser that has reduced pressure drop while ensuring the required thermal performance. The number of pass, the arrangement of the tubes of each pass, and the positions of the inlet and outlet ports on the header are most critical parameters affecting the flow uniformity through all the tubes of the condenser. For the purpose of the performance predictions and the parametric study for the LT condenser, we have developed a 1-dimensional user-friendly performance prediction program that calculates feasibly the phase change of the working fluid in the tubes. An example is presented through the proposed design process and compared with an experiment.

• 공업화학
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• 제10권8호
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• pp.1200-1209
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• 1999

무수프탈산 생산 공정의 조업 조건에서 실측한 이중 고정층 촉매 반응기의 온도분포, 수율 및 냉매의 입출구 온도에 대한 최적 적합으로부터 최적 매개변수 값을 추정함으로써 예측 모델을 구성하였다. 최대 전화율과 수율을 얻을 수 있는 고정층 촉매 반응기를 설계하기 위하여 반응기 길이 및 반경을 변화시켜 그 영향을 고찰하였다. 활성이 균일한 단일 고정층 촉매 반응기의 경우, 반응기 반경 r =0.01241 m에서 전 촉매층 길이 z =2.8 m, 그리고 이중층 반응기의 경우, 반응기 반경 r = 0.01254 m에서 전 촉매층 길이 2,80 m(상부촉매층: 1.88 m, 하부촉매층: 0.92 m)에서 우수한 성능을 보였다. 반응기 반경 변화의 경우, 반경 증가는 냉매로의 열전달 시간의 지연에 의해 열점 온도가 상승하였으며, 반경의 감소는 그 반대의 결과를 보였다.