• Proceedings of the Korea Water Resources Association Conference
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• 1989.07a
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• pp.113-114
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• 1989

원자력, 화력발전소, 제철소 등의 다양한 임해 공업시설로부터 방출되는 냉각용 온배수는 연안일대 해수의 열균형을 파괴시켜 생태계의 보존 및 환경관리에 좋지 못한 영향을 야기케 된다. 이러한 영향은 해안 또는 만내의 수중온도를 전반적으로 높일뿐 아니라 가동중단시 갑자기 수온을 떨어뜨려 해양생물상에 피해를 줄수도 있다. 또한 온배수에 의하여 온도가 상승된 해수가 취수구를 통하여 재순환되어 냉각기능의 부진을 초래하게되면 발전효율 또는 기계가동율을 저하시키게 된다. 이러한 측면에서 온배수의 확산에 대한 정성, 정량적인 예측은 환경영향평가, 취.배수구 설계조건의 산정 등에 매우 중요한 문제라 하겠다. 본 연구는 정지수역으로 유입하는 3차원 정상류 표면온배수 해석모형의 개발로서 개발된 모형의 수치실험을 통하여 온배수 확산의 물리적 특성을 규명한다. 지배방정식에 나타나는 Reynolds 응력항($)과 온도유동 프럭스항($)의 해석에서 필요한 난류모델은 k-$\varepsilon$ 모형에 난류 평균자승 온도유동($) 및 그 감쇄방정식을 추가한 4-방정식 모델로서 구성하였다. 아울러 3차원 정상류 모형에서 야기되는 타원형 방정식을 포물형 방정식의 형태로 전환하여 효과적으로 해석할 수 있도록 모델의 특성을 정리하였다. 본 모델의 검증을 위하여 Lal 및 Rajaratnam(1977)의 물리적 실험값과 비교해본 결과 온배수 거동의 물리적현상이 잘 일치하였다. 또한 McGuirk 및 Rodi(1979)에 의해 개발된 2-방정식 k-$\varepsilon$ 난류모형의 해석결과에 대하여 비교분석을 실시하였다.

• Korean Journal of Crystallography
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• v.14 no.2
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• pp.84-92
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• 2003

The fast pulling is easy to modify the distribution of grown-in defects toward fine size, which can be readily removed by additional treatment. In this experiment, The fast pulled crystals with high pulling late over 1.0 mm/min were grown and their grown-in defect distributions were investigated. In our recent developments in the growth of Cz-Si, it could be found that the cooling rate in a specific temperature range and the uniformity of temperature gradient at solid/liquid interface are more important for the formation of grown-in defect than the pulling rate itself. We analyzed these cooling rates and temperature gradients for the various fast pulled crystals and compared them to the observed formation behavior of the grown-in defects. The effective factor (Ω) for the void defect formation was introduced and it could explain the radial distribution of void defects in the fast-pulled crystals effectively.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.31 no.9
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• pp.915-923
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• 2007

Rubber hoses for automobile radiators are apt to be degraded and thus failed due to the influence of contacting stresses of air and coolant liquid under thermal and mechanical loadings. The aging behaviors of the skin part of the hoses due to thermo-oxidative and electro-chemical stresses were experimentally analyzed. Through the thermo-oxidative aging test, it was shown that the surface hardness IRHD(International Rubber Hardness Degrees) of the rubber increased with a considerable reduction of failure strain as the aging time and temperature increased. On account of the penetration of coolant liquid into the skin part influenced by the electro-chemical degradation(ECD) test the weight of the rubber hose increased, whereas their failure strain and IRHD hardness decreased. The hardness of the hose in the side of the negative pole was the most deteriorated at the test site of the hose skin just below the coolant surface.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.28 no.1
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• pp.101-113
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• 2015

This paper introduces a numerical analysis method for reinforced-concrete(RC) members exposed to fire and proposes considerations in designing RC structures on the basis of the comparison between numerical results and design codes. The proposed analysis method consists of two procedures of the transient heat transfer analysis and the non-linear structural analysis. To exactly evaluate the structural behavior under fire, two material models are considered in this paper. One is "Under-Fire" condition for the material properties at the high temperature and the other one is "After-Cooling" condition for the material properties after cooling down to air temperature. The proposed method is validated through the correlation study between experimental data and numerical results. In advance, the obtained results show that the material properties which are fittable to the corresponding temperature must be taken into account for an accurate prediction of the ultimate resisting capacity of RC members. Finally, comparison of the numerical results with the design code of EN1992-1-2 also shows that the design code needs to be revised to reserve the safety of the fire-damaged structural member.

• Journal of the Korean Society for Nondestructive Testing
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• v.25 no.5
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• pp.368-376
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• 2005

Coolant rubber hoses for automobile radiators can be degraded and thus failed due to the influence of contacting stresses of air and coolant liquid under thermal and mechanical loadings. In this study, for EPDM(ethylene-propylene diene monomer) rubber conventionally used as a radiator hose material the aging behaviors of the skin part due to thermo-oxidative and electro-chemical stresses were nondestructively evaluated. Through the thermo-oxidative aging test, it was shown that the surface hardness IRHD(International Rubber Hardness Degrees) of the rubber increased with a considerable reduction of failure strain. On account of the penetration of coolant liquid into the skin part the weight of rubber specimens degraded by electro-chemical degradation(ECD) test increased, whereas their. failure strain and IRHD hardness decreased largely. The penetration of coolant liquid seemed to induce some changes in inner structure and micro hardness distribution of the rubbers. Consequently, EPDM rubbers degraded by thermo-oxidative aging and ECD could be characterized nondestructively by micro-hardness and chemical structure analysis methods.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.3
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• pp.213-220
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• 2007

Appropriate numerical models for the simulation of off-gas flow in hot area of the vitrification plant have been developed in this study. The models have been applied to analyze the effect of design parameters of real plant and numerical analyses have been performed for CCM(Cold Crucible Melter), pipe cooler and HTF(High Temperature Filter). At first, the effect of excess oxygen and the ratio of oxygen distribution on combustion characteristics in the CCM has been studied. Next, solidification behavior of radio nuclide in the pipe cooler has been numerically modeled and scrutinized. Finally, flow pattern in accordance with the location of off-gas entrance of the HTF has been compared.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.11a
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• pp.69-78
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• 2005

Appropriate numerical models for the simulation of off-gas flow in hot area of the vitrification plant have been developed in this study. The models have been applied to analyze the effect of design parameters of real plant and numerical analyses have been performed for CCM(Cold Crucible Melter), pipe cooler and HTF(High Temperature Filter) At first, the effect of excess oxygen and the ratio of oxygen distribution on combustion characteristics in the CCM has been studied. Next, solidification behavior of radio nuclide In the pipe tooler has been numerically modeled and scrutinized. Finally, flow pattern In accordance with the location of off-gas entrance of the HTF has been compared.

• Korean Chemical Engineering Research
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• v.47 no.4
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• pp.446-452
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• 2009

The behavior of a one-step fixed bed reactor which directly synthesizes dimethyl ether(DME) from Natural Gas was simulated. In the reactor, the prevention of the occurrence of hot spots which can cause deactivation of catalysts is pivotal, since methanol synthesis and dehydration reaction involved in the synthesis of DME are highly exothermic. Therefore, we simulated and compared performance of the reactor with counter-current cooling and pool boiling system that can be applied to a commercial plant. As a result, we found that counter-current cooling system is more effective in terms of CO conversion and DME productivity. However, pool boiling system can operate in a small temperature gradient that can decrease problems caused by hot spot. And, the system can operate in a safer range.

• Korean Chemical Engineering Research
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• v.56 no.3
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• pp.388-403
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• 2018

We investigated design requirements of vent lines for Sodium-Water Reaction Pressure Relief System of Prototype Generation-IV Sodium-Cooled Fast Reactor. We developed design requirements of areas of the rupture disks of the steam generator, a diameter of the gas vent line of the sodium dump tank, a diameter of the gas vent line of the water dump tank, a diameter of the water dump line of the steam generator. With the design requirements, we calculated the time to vent fluid inside the steam generator and analyzed the transient pressure behavior, also evaluated the close pressure value of the isolation valve of the water dump line. Our results are expected to be used as basis information to design Sodium-Water Reaction Pressure Relief System of Prototype Generation IV Sodium-Cooled Fast Reactor.

• Journal of Radiation Protection and Research
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• v.11 no.2
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• pp.139-145
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• 1986

An improved mothod of assessing fuel status by analyzsis of the fission product in the reactor coolant system is proposed. The release mechanism of specific fission products is established for determination of the coefficients in the equations which relate the radioactivities with the amount of defected fuel. Knock-out and migration models are employed in the formulation of the release mechanism. The influence of the tramp uranium is quantified. Sample calculations were made for KNU 1 reactor system using the I-131 and I-133 concentrations in the primary coolant. The estimated number of defected fuel pins in the third and sixth cycles appeared to be $9.34{\pm}1.13\;and\;0.294{\pm}0.092$, respectively.