• Journal of the Korean Institute of Gas
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• v.25 no.3
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• pp.1-8
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• 2021

Among the flare systems that handle discharged substances from safety valves, the knockout drum was a key facility for safety, but the installation standards were not clear, so it was necessary to review the standards acceptable to the workplace and regulatory agencies. After investigating the domestic and foreign technical standards of knockout drums and the deficiencies of previous studies, research was first conducted on the degree of mass discharge, the installation location of the intermediate knockout drum, and the effect of changes in the composition of the discharged material. As a result of the study under the process simulation conditions, the gas-liquid separation of the knockout drum was completed in a small amount of less than 7,500kg/hr. However, when more than that was released, the gas-liquid separation effect was small even with the addition of an intermediate knockout drum. In addition, when the composition ratio of the material easily condensed was increased (molar fraction 10%), the gas-liquid separation effect of the knockout drum increased in the case of mass release. The gas-liquid separation effect was analyzed to be greater when the knockout drum was installed adjacent to the stack than the knockout drum was installed adjacent to the process equipment.

• Journal of Energy Engineering
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• v.25 no.1
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• pp.15-22
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• 2016

The heat transport system transients of Wolsong 2,3,4 nuclear power plants were analysed during abnormal operating conditions. The compliance with requirements of AECB Regulatory Document R-77 for CANDU reactor was estimated. The analysis results showed that for each postulated accident the peak pressure values in the reactor headers are within the acceptance criteria given in ASME code requirements. The effect of LRV that is one of the overpressure protection device was very minor.

• Journal of Ocean Engineering and Technology
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• v.10 no.3
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• pp.24-33
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• 1996

Up to now, most of studies on mechanical properties in friction welded components are about tensile and bending strength. However the fatigue studies on the friction-welded components subjected to repeated stress are not available. The purposes of this study are the development of fundamental design and the development of in-process real-time weld quality evaluation technique by acoustic emission for the bar-to-bar dissimilar friction welding of hydraulic valve spool steels.

• Journal of Welding and Joining
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• v.13 no.4
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• pp.103-112
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• 1995

This study was performed to optimize friction welding conditions of Cr-Mo steel bars used for hydraulic of pneumatic valve spools and to realize the real-time evaluation of weld quality by acoustic emission method. SNCM220, SCM435, SCAM645, and SCM415 steel bars were tested to find optimum conditions of friction welding. Auantitative equations which exhibit the relations of tensile strength, elongation, reduction of area and energy absorption with friction heating time were obtained by the experiment. Acoustic emission was also performed in the friction weldig process, and the real-time evaluation was enabled to find the optimum range of weld strength. Finally, the strength and toughness of welded joints were interpreted by the sem analysis of tensile fracture surfaces.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.10a
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• pp.371-376
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• 1995

CANDU-6형 원자로의 정지냉각계통(Shutdown Cooling System, SDCS)은 영출력 고온상태의 원자로를 상온상태로 냉각시킬 수 있도록 설계되었다. 본 해석은 증기발생기와 복수기증기방출밸브(CSDV) 및 정지냉각펌프를 이용한 정상냉각과 열수송펌프를 이용한 26$0^{\circ}C$부터 냉각 및 정지냉각펌프를 이용한 26$0^{\circ}C$부터 냉각의 두 가지 비정상냉각에 대해서 중수로 계통설계의 열수력 해석코드인 SOPHT 코드를 사용하여 해석하였다. 해석결과에 따라 주요기기들의 냉각천이에 따른 운전부하(service loadings)조건이 주어졌으며 또한 정지냉각계통은 열수송계통과 관련 보조계통을 정지냉각계통 열교환기 2차측에서 비등이 발생하지 않고 정상냉각 허용한계인 2.8$^{\circ}C$/min를 만족하면서 냉각할 수 있음을 확인하였다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11a
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• pp.369-375
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• 1996

가압경수로의 기동과 냉각시 발생할 수 있는 저온과압사고는 원자로 압력용기의 취성파괴를 유발할 위험이 있다. 따라서 발전소는 저온과압을 방지하기 위해 기술지침서의 온도-압력 곡선을 토대로 운전온도에 따른 압력경계를 제한하고 있으며, 과압방지설비로 가압기 PORV나 잔열제거계통의 방출밸브를 갖추고 있다. 미 NRC에서는 GL90-06을 통해 저온과압사고에 대한 안전성 분석을 권고하고 있으며, 이에 따른 표준 기술 지침서를 제시하였다. 국내 가동 원자력발전소중 영광 3,4호기 이후에는 설계시 이를 반영하였으나, 타 발전소에는 반영되질 않았다. 이 논문에서는 이들 운전중인 가압경수로의 저온과압사고에 대한 안전성 분석을 수행하기 위해 개발한 안전성 평가 방법을 제시하였다.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.771-776
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• 1998

울진 원전 3,4 호기를 대상으로 MAAP4.0.2 코드를 이용하여 발전소 정전사고를 모의/분석했다. 본 분석에서는 사고진행에 따른 일.이차계통의 상태변화를 원자로용기 파손때까지 상세 파악하였다. 사고관리 관점에서, 발전소 정전사고는 이차측의 대기방출밸브를 통한 강제감압에 의해 사고진행을 완화할 수 있으며 이러한 운전원 조치에 의한 완화효과를 검토하였다 그 결과 감압시작 2시간후에 일차측은 약 24$^{\circ}C$ 의 과냉각도를 보이며 안정되었고. 사고시작 1시간 후부터 3시간 동안의 강제감압이 성공한 경우, 노심노출시간 기준으로 약 2시간의 지면효과가 있었다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05b
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• pp.160-165
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• 1996

중수로형 원전에서 일차측 냉각수를 순환시키는 주연수송펌프가 정상운전중 갑자기 정지하는 사고를 강제순환 상실사고라 한다. 강제순환 상실사고는 주열수송계통을 과도압력상태로 만들며, 일반적으로 펌프에 공급되는 IV등급전원 상실사고와 기계적 손상에 의한 주열수송펌프 고착사고로 분류할 수 있다. 본 논문에서는 강제순환 상실사고에 대하여 중수로계통설계의 열수력 해석코드인 SOPHT를 이용하여 주열수송계통의 과도압력상태를 해석하였다. 카나다 원자력 규제위원회(AECB)의 과압 방지조건인 R-77 요구조건에 적절한 유효트립변수를 결정하기 위한 해석이 수행되었으며, 증기발생기 오염상태와 액체방출밸브 작동여부가 고도압력상태에 미치는 영향을 고찰하여 보수적 조건을 제시하였다. 또한 위와같이 결정된 보수적 조건을 근거로 ASME 코드에 명시된 과압 한계치에 대한 만족여부와 과도압력상태에 따른 주열수송계통의 열수력학적 거동을 고찰하여 보았다. 해석결과, 강제순환상실사고시 주열수송계통은 R-77 요구조건에 적합한 원자로트립변수에 따라 안정화되었으며, 계통의 최대압력은 ASME 코드가 규정한 한계치내에 있음을 알 수 있었다.

• Journal of Ocean Engineering and Technology
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• v.10 no.2
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• pp.69-76
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• 1996

In-process quality control and high reliability of the weld are the major concerns in applying friction welding to the economical and qualified mass-production. Experimental examinations and quantitative analysis were performed for the optimiaztion of similar friction welding of hydraulic valve spool steels(SNCM220, SCM435, SACM645, SCM415, ${\varphi}24). The quantitative correlations were found between the initial cumulative counts of acoustic emission(AE) occurring during plastic deformation periods of the welding and the fatigue life as well as weld strength and welding conditions. A real-time evaluation system was developed for the friction weld quality by AE.

• Journal of the Korea Institute of Military Science and Technology
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• v.7 no.2 s.17
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• pp.41-47
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• 2004

In this paper, simulations of the underwater discharge system with compressed air are performed to predict dynamic characteristics of the system and to find optimal opening trajectories of the expulsion valve. Major components of the system are defined and their governing equations are derived to make up the mathematical model. The compressed air discharge method is affected largely by the discharge depth, and therefore the opening trajectories according to the discharge depth should be found to satisfy the demands of discharge performances. Simulation results are compared with experimental data to confirm the validity of the system model.