• 한국해양공학회:학술대회논문집
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• 한국해양공학회 2004년도 학술대회지
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• pp.365-369
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• 2004

Recently, Inconel 625 is used widely in offshore processing piping in order to extend the maintenance tenn and improve the quality of anti-corrosion. According to the resistance to attack in various corrosive media at temperatures from $200^{\circ}C$ to aver $1090^{\circ}C$, in combination with good low- and high-temperature mechanical strength. In general, High quality weldments for this material are readily produced by commonly used processes. in recent years, the flux cored arc welding(FCAW) process is becoming more popular due to higher deposition rate and a better weld quality as compared to the shielded metal arc welding (SMAW) process, at the same time, exhibiting equally good weld metal toughness similar to the SAW process. In this study, the weldability and weldment characteristics(mechanical properties and corrosive environment) of Inconel 625 are considered in FCAW weld associated with the several weld shielding gases($80\%Ar\;+\;20\%\;CO_2,\;50\%Ar\;+\;50\%\;CO_2,\;100\%\;CO_2$) in viewpoint of welding productivity.

• 한국기계가공학회지
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• 제17권4호
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• pp.23-31
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• 2018

Stress of a steam separator, equipment of the high-pressure (HP) evaporator for a HRSG, was analyzed and evaluated according to ASME Boiler & Pressure Vessel Code Section VIII Division 2. First, from the analysis results of the piping system model of the HP evaporator, reaction forces of the riser tubes connected to the steam separator, i.e., nozzle loads, were derived. Next, a finite element model of the steam separator was constructed and analyzed for the design pressure and the nozzle loads. The results show that the maximum stress occurred at the bore of the riser nozzle. The primary membrane stresses at the shell and nozzle were found to be less than the allowable stress. Next, the steam separator was analyzed for the steady-state operating conditions of operating pressure, operating temperature, and nozzle loads. The maximum stress occurred at the bore of the riser nozzle. The primary plus secondary membrane plus bending stress at the shell and nozzle was found to be less than the allowable stress.

• 한국전자통신학회논문지
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• 제16권2호
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• pp.347-354
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• 2021

화학공장과 같은 장치산업은 고온·고압·유독성 유체가 배관을 통하여 각종 설비들 사이를 이동한다. 온도변화, 진동, 지진, 지반침하와 같은 주변환경의 변화에 의한 배관의 위치 이동과 파손은 인명피해를 수반하는 큰 사고로 연결되는 경우가 많다. 이러한 사고를 방지하기 위하여 배관에 가해지는 각종 충격을 흡수하고, 보완하여 사고를 미연에 방지하기 위한 여러 가지 종류의 익스펜션 조인트(Expansion Joint)를 사용한다. 따라서 사용된 익스펜션 조인트의 변형을 측정하고, 수명을 예측하는 것은 대형사고를 방지하기 위하여 매우 중요하다. 본 논문에서는 익스펜션 조인트의 변형을 일종의 모션으로 이해하고, Hall Effect Sensor와 9-Axis Sensor를 사용하여 변화를 측정하였다. 그리고 범용의 마이컴보드 아두이노와 C언어를 사용하여 측정된 데이터를 모으고, 분석하여 익스펜션 조인트의 변형을 예측할 수 있는 시스템에 대하여 연구하였다.

• Journal of Welding and Joining
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• 제26권1호
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• pp.50-55
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• 2008

A low alloy-steel(2.25Cr-1.0Mo) has been widely used for boiler piping, header and tubes in high temperature and pressure conditions of the thermal power plant. It is common knowledge that the repair welding is permitted two or three times by customary practice rule, but there is no regulation to limit the number of repair welding base on the study heat-affected zone(HAZ), which is the weakest zone when repair welding is under taken, by experiments about the metallographic degradation and mechanical properties. Therefore, this study aims to verify the reliability of 5 times repair welding through conducting the experimental observation in the mechanical and the metallographic change on HAZ varying repair welding times. In results of the experiments, it is concluded that the reliability was kept in HAZ even up to the fifth repairs.

• 대한용접접합학회:학술대회논문집
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• 대한용접접합학회 2004년도 추계학술발표대회 개요집
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• pp.141-143
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• 2004

The experimental simulation welds using 3kinds of 70ksi titania based flux-cored consumables were performed on 24 inches 24.6-thick API 5L Gr. B pipe with relatively high current, over 300A and four different Post Weld Heat Treaonent(PWHT) conditions at $625^{circ}C$ were applied to each consumable test coupon. It is well known that, in common welding processes such as Submerged Arc Welding(SAW) or Flux Cored A.c Welding(FCAW), the cooling rates in as-deposited weld bead are normally so ,apid that actual precipitation of microalloy carbonitrides, Nb(C,N) or V(C,N) is not likely to occur in the as-welded weld metal, however, during stress relief or PWHT the operation of precipitation can reduce the impact properties of the weld metal. As results of mechanical testing, it is concluded that PWHT at $625^{circ}C$ is detrimental to weld metal impact toughness of Ti-B type flux- cored (FC) welding consumables regardless of the amount of Nb and V, but two optima were exhibited, one at 800ppm Ti, 75ppm 5 and another 360ppm Ti, 54ppm 5.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 추계학술발표회논문집(1)
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• pp.358-363
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• 1995

A study on passive cooling systems for concrete containment of advanced pressurized water reactors has been performed. The proposed passive containment cooling system (PCCS) consist of (1) condenser units located inside containment, (2) a steam condensing pool outside containment at higher elevation, and (3) downcommer/riser piping systems which provide coolant flow paths. During an accident causing high containment pressure and temperature, the steam/air mixture in containment is condensed on the outer surface of condenser tubes transferring the heat to coolant flowing inside tubes. The coolant transfers the heat to the steam condensing pool via natural circulation due to density difference. This PCCS has the following characteristic: (1) applicable to concrete containment system, (2) no limitation in plant capacity expansion, (3) efficient steam condensing mechanism (dropwise or film condensation at the surface of condenser tube), and (4) utilization of a fully passive mechanism. A preliminary conceptual design work has been done based on steady-state assumptions to determine important design parameter including the elevation of components and required heat transfer area of the condenser tube. Assuming a decay power level of 2%, the required heat transfer area for 1,000MWe plant is assessed to be about 2,000 ㎡ (equivalent to 1,600 of 10 m-long, 4-cm-OD tubes) with the relative elevation difference of 38 m between the condenser and steam condensing pool and the riser diameter of 0.62 m.

• Nuclear Engineering and Technology
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• 제48권4호
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• pp.893-905
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• 2016

Numerous advanced reactor concepts have been proposed to replace light water reactors ever since their establishment as the dominant technology for nuclear energy production. While most designs seek to improve cost competitiveness and safety, the implausibility of doing so with affordable materials or existing nuclear fuel infrastructure reduces the possibility of near-term deployment, especially in developing countries. The organic nuclear concept, first explored in the 1950s, offers an attractive alternative to advanced reactor designs being considered. The advent of high temperature fluids, along with advances in hydrocracking and reforming technologies driven by the oil and gas industries, make the organic concept even more viable today. We present a simple, cost-effective, and safe small modular nuclear reactor for offshore underwater deployment. The core is moderated by graphite, zirconium hydride, and organic fluid while cooled by the organic fluid. The organic coolant enables operation near atmospheric pressure and use of plain carbon steel for the reactor tank and primary coolant piping system. The core is designed to mitigate the coolant degradation seen in early organic reactors. Overall, the design provides a power density of 40 kW/L, while reducing the reactor hull size by 40% compared with a pressurized water reactor while significantly reducing capital plant costs.

• 설비공학논문집
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• 제14권1호
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• pp.31-37
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• 2002

This paper is concerned with the development of a new method for making and separating ice and saving floated ice by installing an evaporation plate at in-water within a storage tank. In a conventional harvest-type ice storage system, a tank saves ice by separating a formed ice from an installed evaporation plate, which is located above an ice storage tank as an ice storage system. A new harvest-type method shows very good heat transfer efficiency than a convectional method. It is because the evaporation panel is directly contacted with water in a storage tank. Also, at a conventional system a circulating pump, a circulating water distributor and a piping are installed, but these components are not necessary in a new method. In this study two kinds of ice storage systems are experimentally investigated to study the thermal characteristics of ice storage tanks. The results showed discharge of cold capacity of new type indicated the high values about 30~40% based on five time of drive, the temperature difference of inlet/outlet occurred the big range about $1.3^{\circ}C$. So, the new type which makes ice in water showed superiorly.

• Journal of Welding and Joining
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• 제13권2호
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• pp.12-24
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• 1995

최근에 국내 화력발전설비도 사용 기간이 30년을 넘게 됨에 따라, 고온설비의 경년열화도 평가 및 수명예측 기술에 대한 연구가 활발해지고 있다. 본 논문에서는 l965년부터 사용되어 노 후된 영월화력발전소 2호기의 주증기 파이프를 대상으로 실시한 열화도 및 수명평가 결과를 보고하였다. 주증기관의 취약부인 맞대기 용접부, 지류 용접부, Y부 및 T부 등의 용접부에 대해 표면복제법, 경도측정법을 사용하여 수명평가를 실시하였으며, 비파괴 검사에 의해 균열이 탐지된 경우에는 수명평가 컴퓨터 코드를 사용하여 균열성장에 의한 잔여수명을 계산하였다. 또한 파이프 모재의 잔여 수명은 해석적 방법에 의해 정량적으로 잔여수명을 계산한 후, 외경 패출량 측정, 입계부식법 등에 의해 재질 열화도를 정성적으로 평가하였다. 본 논문에서 사용한 기법 이외의 방법을 사용하여 수명평가 정확도를 개선하는 방향에 대한 의견도 제시하였다.

• 해양환경안전학회지
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• 제23권5호
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• pp.541-548
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• 2017

본 연구에서는 해양플랜트설비 건조 현장에서 사용되고 있는 기존 고온 오일 플러싱 장비에 대한 성능개선을 위해 기존의 플러싱 장치에 사용되던 오일에 질소가스를 혼합한 고온 오일 플러싱 시스템에 대하여 국제표준화기구 코드(ISO code)를 기준으로 이론적 연구를 수행하였다. 연구를 위해 오일-질소가스 혼합유체 플러싱 시스템 공정을 설계 후 청정성능에 영향을 주는 혼합유체의 혼합비율, 온도, 레이놀즈수 및 액상분율 등에 대한 공정모사 결과도 분석하였다. 그 결과 관 직경과 가스상의 체적분률이 일정한 상태에서 혼합유체의 체적유량이 증가될수록 수평 유압배관 입출구의 액상분율 차이 ${\Delta}{\alpha}_L$ 값은 증가하게 되고 배관길이 방향의 위치에 따라 오일과 질소가스 기포 사이의 상분포가 달라짐을 확인했다. 이러한 상분포의 변화는 오일-질소가스 혼합유체 플러싱 시스템의 청정성능에도 커다란 영향을 줄 것으로 예상된다.