• Journal of Ocean Engineering and Technology
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• v.13 no.3 s.33
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• pp.100-107
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• 1999

Due to the high temperature and pressure, the materials of pipeline in power plant are degraded by creep damage. So far, many conventional measurement techniques such as replica method, electric resistance method, adn hardness test method for creep damage have been used. Among them, the replica method has mainly been used for the inspection of components. But this technique is restricted to the applications at the surface of the objects and cannot be used to material inside. In this paper, the measuring methods of evaluation by using ultrasonic attenuation and electric resistance for the creep detection of creep damage in the form of cavities on grain boundaries or intergranular microcracks were carried out. Absolute measuring method of quantitave ultrasonic attenuation technique for 1Cr0.5Mo material degradation was analyzed for determining the creep degradation steps using life prediction formula. As a result of measurement for creep specimens, we founded that the coefficient of utrasonic attenuation was increased as the increase of creep life fracton(${phi}c$) and the decreasing rate of wlwctric resistance was also increased.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.14 no.1
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• pp.32-37
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• 2018

When designing high temperature piping system, creep phenomena must be considered. Since ASME code does not provide detailed methods of design by rule (DBR) for high temperature piping, Finite element analysis should be performed. However, In the case of piping system with frequent design changes, creep analysis of the entire piping system for every change is ineffective and practically impossible. Therefore, based on elastic and elastic-plastic analysis, which takes a relatively short time, the creep stress is predicted by using elastic follow-up factor method provided in R5 code and plastic-creep analogy presented by Hoff. The predicted creep stress for a virtual piping system was compared with the creep analysis result and the two results showed similar stress relaxation tendency in time.

• Journal of Ocean Engineering and Technology
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• v.12 no.2 s.28
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• pp.65-70
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• 1998

In this report, the creep properties and creep life estimation by Larson-Miller Parameter(LMP) Method for 2.25Cr1Mo steel to be used as power plant tubes or other components were presented at the high temperatures of 500, 550, and $600^{\circ}C$. It was confirmed experimentally and quantitatively that a creep life estimation equation at such various high temperatures was well derived by LMP and could be used very effectively within the creep life of 10$^3$ hours, but very unreliable and even dangerous for design in a long term of creep life such as 10$^4$ or $10^5$ hours.

• Proceedings of the KSME Conference
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• 2000.04a
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• pp.37-42
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• 2000

The boiler tubes and steam Pipes operating both at high temperature and pressure for a long period of time in a power plant are degraded by creep because of internal pressure. So, the remaining life of a component is evaluated by the creep rupture strength. Although the conventional method to evaluate the creep damage is widely used, it has some disadvantages such as requires large size specimen and long employed to evaluate the correlation between fracture toughness and evaluation time. Recently, new method so called "small lunch test' is used to evaluate degradation of creep. In this study, a conventional creep test and a small punch test are conducted using 2.25Cr-1Mo steel which is mainly used for the boiler tubes and steam pipes in power plant. The creep life, approximately 1,500 hrs, is determined by conventional method under a severe condition then specimens for a small Punch test are obtained after certain time intervals such as 1/4, 1/2 and 3/4 of final rupture time, respectively.

• Proceedings of the Membrane Society of Korea Conference
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• 1996.06a
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• pp.149-153
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• 1996

반도체 소자 제조 공정이 고 집적화 됨에 따라 습식 세정방법에 의한 세정공정의 중요성이 더욱 증가 되어지고 있으며, 특히 그 중에서 전체 세정공정의 약 절반을 차지하고 있는 Deionised water에 의한 rinsing 공정의 경우 ultrapure water의 quality가 최근 지속적으로 향상이 되어짐에 따라 많은 발전을 자져 왔다. 일반적으로 Deionised water에 함유하고 있는 TOC(total oxidisable components), bacteria, metallic impurity, desolved oxygen cencentration, colloidal material impurity (예를 들면 Silica, oraganic substrate)등은 ultra pure water의 quality를 결정하는데 매우 중요한 factor로 작용하고 있으며, 이러한 불순물들이 반도체 제조공정중 wafer surface에 흡착되어 졌을때 여러형태의 defect들을 유발한다고 알려져 있다. 그러나 pseudommonas, flavobacterlum, alcaligene등의 기 얄려진 bacteria들의 경우 Deionised water를 supply해주는 배관의 Inner surface에 잘 흡착 되지만 고온의 water 혹은 과산화수소수($H_{2}O_{2}$) 를 이용하여 주기적으로 처리 해줌으로 인하여 이에 대한 문제점을 어느정도 최소화 시킬수 있다. 위의 두가지 방법중 전자의 경우 chemical을 사용하지 않고, 유지 및 관리가 간편하며, 용존산소량을 줄일수 있다는 점에서 장점이 있으나, 전 ultra pure water의 system이 열적으로 안정해야 하고 경제적인 문제가 수반하는 단점을 가지고 있다. 후자의 경우, 미량의 과산화수소수 (1~10,000 ppm)를 이용해 처리 해주는 방법의 경우 경제적으로 큰 장점이 있고, 처리가 단순하다는 장점이 있으나 과산화수소수 자체에 포함하고 있는 높은 impurit level, 그리고 처리후 장시간의 flushing time을 가져야 한다는 단점등이 존재 하고 있다.

• The Bulletin of The Korean Astronomical Society
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• v.37 no.2
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• pp.151.1-151.1
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• 2012

우주발사체와 발사지원설비를 연결하여 추진제 공급과 전기신호 송수신 등을 가능하게 하는 메커니즘을 엄브리칼 장치라고 한다. 국내 우주발사체의 경우 액체산소와 케로신을 추진제로 사용하며, 질소, 공기 및 헬륨 등의 가스를 밸브구동, 공간 퍼지, 추진제 가압에 이용한다. 본 논문에서는 우주센터의 발사대설비에 적용된 엄브리칼 장치 중 추진제 및 고압가스 공급을 위한 자동체결장치(auto coupling device)의 구성, 기능 및 발사 준비를 위한 프로세스에 대해 기술하고 있다. 자동체결장치는 발사체 하부 두 곳에 연결되며, 산화제 공급측의 체결장치(coupling device 1)와 연료 공급측의 체결장치(CD 2)로 구성된다. 이 장치는 발사체와의 접촉면에서 기밀을 확보한 상태에서 내부의 탱크, 밸브, 인터스테이지 등에 추진제 및 각종 가스를 공급하는 통로역할을 하며, 발사준비가 완료된 후에는 발사체 이륙 전 또는 이륙과 동시에 발사체로부터 자동으로 분리된다. 각각의 체결장치 구성품으로는 발사체 이륙시 발생하는 고온의 화염으로부터 장치를 보호하는 PD(protective device), 접촉면에 기밀을 제공하고 추진제 누출을 방지는 MCP(multi-channel plate), 접촉면을 보호하기 위한 덮게, 각종 연결 배관의 전진과 후진을 위한 캐리지, 발사체와의 체결을 지지하는 그립 등이 있다. 발사 준비를 위해서 사전에 장치의 독립운용시험을 통해 각 구성품의 상태와 기능을 점검하고 장치의 작동성을 검증한다. 이후 발사체를 모사하는 기체 및 관제설비와 종합적으로 연계 시험과 모사시험을 수행하여 최종적으로 발사준비상태를 확인하게 된다. 이러한 자동체결장치의 운용 경험은 한국형발사체의 지상지원설비 개발에 활용할 수 있을 것이다.

• Journal of the Korean Society of Safety
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• v.20 no.3 s.71
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• pp.34-41
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• 2005

For assessing residual lift of the steam pipe in fossil power plants, inspections and analysis are usually focused on the critical locations such as butt welds, elbows, Y-piece and T-piece of the steam pipes. In predicting the residual life of T-piece, determination of local stress near welds considering system load as well as internal pressure is not a simple problem. In this study, stress analysis of a T-piece pipe was conducted using a three-dimensional model which represents the T-piece of a domestic fossil power station. Elastic and elastic-creep analysis showed the maximum stress level and its location. Residual creep rupture life was also calculated using the stress analysis results. It was argued that the calculated life is reasonably same as the measured one. The stress analysis results also support life prediction methodology based on in-field replication technique.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.06a
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• pp.110-120
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• 2005

For utilizing vitrification to treat low and intermediate level waste, industrial pilot plant was designed and constructed in October 1999 at Daejon, Korea through the joint research program among NETEC, MOBIS and SGN. More than 70 tests were performed on simulated IER, DAW etc. including key nuclide surrogate(Cs, Co); this plant has been shown to vitrify the target waste effectively and safely, however, some dust are generated from the HTF(High Temperature Filter) as a secondary waste. In case of long term operation, it is also concerned that pipe plugging can be occurred due to deposited dust in cooling pipe namely, connecting pipe between CCM(Cold Crucible Melter) and HTF. In this regard, we have developed the special complementary system of the off-gas treatment system to recycle the dust from HTF to CCM and to remove the interior dust of cooling pipe. Main concept of the dust recycling is to feed the dust to the CCM as a slurry state; this system is regarded as of an important position in the viewpoint of volume reduction, waste disposal cost and glass melt control in CCM. The role of DRS(Dust Recycling System) is to recycle the major glass components and key nuclides; this system is served to lower glass viscosity and increase waste solubility by recycling B, Na, Li components into glass melt and also to re-entrain and incorporate into glass melt like Cs, Co. Therefore dust recycling is helpful to control the molten glass; it is unnecessary to consider a separate dust treatment system like a cementation equipment. The effects of Dust Cleaner are to prevent the pipe plugging due to dust and to treat the deposited dust by raking the dust into CCM. During the pilot vitrification test, overall performance assessment was successfully performed; DRS and Dust Cleaner are found to be useful and effective for recycling the dust from HTF and also removing the dust in cooling pipe. The obtained operational data and operational experiences will be used as a basis of the commercial facility.

• Journal of Energy Engineering
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• v.25 no.4
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• pp.124-132
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• 2016

In order to estimate the effect of flow distributors connected to an upper nozzle of CMT(Core Makeup Tank) on the thermal-hydraulic characteristics in the tank, a simplified 2 inch Small Break Loss of Coolant Accident(SBLOCA) was simulated by skipping the decay power and Passive Residual Heat Removal System(PRHRS) actuation. The CMT is a part of safety injection systems in the SMART (System Integrated Modular Advanced Reactor). Each test was performed with reliable boundary conditions. It means that the pressure distribution is provided with repeatable and reproducible behavior during SBLOCA simulations. The maximum flow rates were achieved at around 350 seconds after the initial opening of the isolation valve installed in CMT. After a short period of decreased flow rate, it attained a steady injection flow rate after about 1,250 seconds. This unstable injection period of the CMT coolant is due to the condensation of steam injected into the upper part of CMT. The steady injection flow rate was about 8.4% higher with B-type distributor than that with A-type distributor. The gravity injection during hot condition tests were in good agreement with that during cold condition tests except for the early stages.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.41 no.11
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• pp.767-773
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• 2017

Printed Circuit Heat Exchanger (PCHE) has an advantage for exchanging thermal energy between high-pressure and high-temperature fluids because its core is made by diffusion bonding method of accumulated metal thin-plates which are engraved of flow channel. Moreover, because it is possible that the flow channel can be micro-size hydraulic diameter, the heat transfer area per unit volume can be made larger than traditional heat exchanger. Therefore, PCHE can have higher efficiency of heat transfer. The smaller channel size can make the larger heat transfer area per unit volume. But if high pressure fluid flows inside the channel, the channel wall can be deformed, the structure and shape of flow channel and header have to be designed appropriately. In this study, the design methodology of PCHE channel in high pressure environment based on pressure vessel codes was investigated. And this methodology was validated by computational analysis.