• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.134.2-134
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• 2002

• Proceedings of the Korea Water Resources Association Conference
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• 2018.05a
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• pp.108-108
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• 2018

상수관의 노후화 혹은 공사 중 작업자의 실수, 또는 자연재해 등에 의해 상수관망 내 파손 관이 발생할 경우 파손된 관의 보수 및 교체 작업을 위해서는 파손 관과 인접한 밸브를 차폐하게 된다. 이로 인하여 관망의 일부 지역에 물 공급이 차단되는 단수구역이 발생하게 되며, 단수구역은 밸브를 닫음으로 인해 파손 관과 함께 격리되는 직접고립지역(segment)과 직접고립지역을 차폐함으로써 의도치 않게 수원으로부터 물 공급이 차단되는 간접고립지역(unintended isolation)으로 구분할 수 있다. 간접고립지역은 차폐된 직접고립지역으로 인해 수원으로부터의 유일한 용수공급 노선이 차단되어 발생한다. 관 파손에 의한 단수 피해를 현실적으로 모의하기 위해서는 밸브위치에 따른 단수구역을 정확히 산정할 필요가 있다. 단수구역은 파손관의 위치뿐만 아니라 차단 밸브의 개수 및 위치에 따라 달라진다. 따라서, 관 파손에 의한 단수피해를 최소화하기 위해서는 각 관로의 파손확률과 절점의 중요도를 고려하여, 적절한 밸브의 위치를 선정해야 한다. 본 연구에서는 관 파손에 따른 단수상황을 모의하여 파손 관에 의한 직, 간접 단수구역을 탐색한 후, 단수용량을 파악하고 이를 최소화하기 위한 밸브의 적정 위치를 최적화 알고리즘을 이용하여 결정하는 방안을 제시하였다.

• Aerospace Engineering and Technology
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• v.3 no.1
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• pp.97-102
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• 2004

Propulsion System provides the required velocity change impulse for orbit transfer from parking orbit to mission orbit and three-axis vehicle attitude control impulse. KOMPSAT-2 propulsion system(PS) is an all-welded, monopropellant hydrazine system. The PS consists of the subassemblies and components such as Thrusters, Propellant Tank, Pressure Transducer, Propellant Filter, Latching Isolation Valves, Fill/Drain Valves, interconnecting propellant line assembly, and thermal hardwares for operation-environment control of the PS. This paper summarizes a development process of the liquid propulsion system from the design engineering up to the test and evaluation.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.5 no.1
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• pp.9-13
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• 2009

The containment local leakage rate testing in nuclear power plants is performed in accordance with ANSI/ANS-56.8(1994) in Korea. Two methods, the make-up flow rate and the pressure decay, are used for LLRT. Though ANSI/ANS-56.8 does not define clearly the minimum test duration for the make-up flow rate method, it requires obtaining the data after reaching the stable condition. Thus the prerequisite stable condition for data acquisition and the test period for type "C" LLRT is differently applied to each NPPs. Therefore, this study presents a unified test criteria for data stabilization and test duration through experiments to improve the test reliability for type "C".

• Aerospace Engineering and Technology
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• v.5 no.2
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• pp.85-89
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• 2006

Propulsion System provides the required velocity change impulse for orbit transfer from parking orbit to mission orbit and three-axis vehicle attitude control impulse. New LEO Satellite propulsion system (PS) will be an all-welded, monopropellant hydrazine system. The PS consists of the subassemblies and components such as Thrusters, Propellant Tank, Pressure Transducer, Propellant Filter, Latching Isolation Valves, Fill/Drain Valves, interconnecting propellant line assembly, and thermal hardwares for operation-environment control of the PS. In this study, preliminary design process of LEO Satellite propulsion system will be summarized.

• 유체기계공업학회:학술대회논문집
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• 2002.12a
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• pp.493-498
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• 2002

The letdown system of pressurized water reactor (PWR) nuclear fewer plants had experienced instabilities in letdown system due to unacceptable flow characteristics of control valves. The Korean Standard Nuclear Power Plants (KSNPs) have three flow paths in parallel for letdown new control. Each flow path consists of two offices and one isolation valve. This study evaluates the effect of orifice arrangement and valve stroke time of letdown isolation valve on the system transients because sudden flow changes due to valve actuation can generate high pressure peaks in letdown line. A pressure transient analysis has been preformed to evaluate the impact of dynamic transients. This analysis uses MMS which is a simulation code developed by EPRI based on the method of characteristics. The result shows that the pressure peak is reduced in the continuous arrangement but negligible. Additionally, it shows that the stroke time of linear type flog valve greater than 15 seconds can give more stable performance.

• Journal of Korea Water Resources Association
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• v.39 no.2 s.163
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• pp.89-98
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• 2006

To evaluate the pipe failure impact, current methodologies consider only a broken pipe as the impacted area. However, these approaches are accurate if the broken pipe is the only area isolated from tile system. Depending on the number and locations of on-off valves, more pipes which are adjacent to a broken pipe may be isolated. Using the concept of Segment suggested by Walski, the methodology evaluating the pipe failure impact incorporated with on-off valve locations has been suggested by Jun. However, a segment cannot account for all possible pipe failure impacted areas since it does not consider additional failures, namely the network topological failure and the hydraulic pressure failure. For this reason, a methodology which can consider the network topology and hydraulic pressure limitation as well as on-off valve locations is suggested. The suggested methodology is applied to a real network to verify its applicability As results, it is found that a single pipe failure can affect huge areas depending on the configuration of on-off valves and the network topology. Thus, the applicability of the suggested methodology for evaluating the pipe failure impacts on a water distribution network is proved.

• 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 computational fluids engineering
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• v.20 no.3
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• pp.87-93
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• 2015

In this study, a numerical analysis was performed to simulate the thermal-hydraulic response of the secondary side of a steam generator(SG) model equipped with an orifice-type SG outlet flow restrictor to a main steam line break(MSLB) at a pressurized water reactor(PWR) plant. The SG analysis model includes the SG upper steam space and the part of the main steam pipe between the SG outlet and the broken pipe end. By comparing the numerical calculation results for the present SG model to those obtained for a simple SG model having no flow restrictor, the effects of the flow restrictor on the thermal-hydraulic response of SG to the MSLB were investigated.

• Proceedings of the Korean Vacuum Society Conference
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• 2010.02a
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• pp.330-330
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• 2010

하나로 노심에서 발생하는 열중성자를 감속재인 액체수소층을 통과시켜 냉중성자를 생산 하는 설비인 냉중성자원 시설은 초경량 합금, 신소재 및 DNA 구조연구 등의 첨단기술연구에 유용한 도구로 활용될 계획이며, 현재 원자력연구원에서는 냉중성자원 시설을 개발하여 제작 설치하였고, 이 장치들에 대해 기능시험을 수행하였다. 냉중성자원 시설계통에서 가스블랭킷계통은 수소의 외부누출을 방지하고, 진공용기를 포함한 수조내기기 내부로 공기 및 경수가 유입되지 않도록 하여 냉중성자원을 보호하기 위한 역할을 수행한다. 또한 가스블랭킷계통의 구성은 가스공급장치($N_2$ 및 He 가스 실린더로부터 가스공급 기능), 질소충압탱크, 진공박스, 수소박스, 밸브박스 및 각 구역별 독립 배관 등으로 되어있다. 이동식 진공배기장치는 가스블랭킷계통에서 사용하기 위해 특수하게 제작된 장치로서 진공계통과 수소계통의 초기충진 시 또는 계통배기 시 잔류가스를 제거하거나, 블랭킷가스의 오염검사를 위한 시료채취 기능 등을 수행할 수 있도록 되어있다. 본 논문에서는 냉중성자원장치 내의 수소계통 및 진공계통의 배관과 기기를 외기와 경수로부터 안전하게 격리시키기 위해서 제작설치 적용된 가스블랭킷계통에서 이동식 진공배기장치를 이용하여 잔류가스 제거방법과 각 가스블랭킷 영역으로부터 시료를 채취하여 수행된 산소농도 분석에 대해 기술하였다.