• 대한기계학회:학술대회논문집
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• 대한기계학회 2003년도 춘계학술대회
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• pp.1633-1638
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• 2003

In case that in-leakage through the valve disk occurs, a numerical study is performed to estimate on thermal stratification phenomenon in the Safety Injection piping connected with the Reactor Coolant System piping of Nuclear Power Plant. As the leakage flow rate increases, the temperature difference between top and bottom of horizontal piping has the inflection point. In the connection point of valve and piping, the maximum temperature difference between top and bottom was 185K and occurred in the condition of 10 times of standard leakage flow rate. In the connection point of elbow and horizontal piping, the maximum temperature difference was 145K and occurred in the condition of 15 times of standard leakage flow rate. In the vertical piping of Safety Injection piping, the near of connection point between elbow and vertical piping showed the outstanding thermal stratification phenomenon in comparison with another region because of turbulent penetration from Reactor Coolant System piping. In order to prevent damage of piping due to the thermal stratification when in-leakage through the valve disk occurs, the connection points between valve and piping, and the connection points between elbow and piping need to be inspected continually.

• Nuclear Engineering and Technology
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• 제53권8호
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• pp.2477-2487
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• 2021

To improve safety analysis technology for a nuclear reactor containment considering an interaction between a reactor coolant system (RCS) and containment, this study aims at an experimental investigation on the integrated simulation of the RCS and containment, with an integral effect test facility, ATLAS-CUBE. For a realistic simulation of a pressure and temperature (P/T) transient, the containment simulation vessel was designed to preserve a volumetric scale equivalently to the RCS volume scale of ATLAS. Three test cases for a steam line break (SLB) transient were conducted with variation of the initial condition of the passive heat sink or the steam flow direction. The test results indicated a stratified behavior of the steam-gas mixture in the containment following a high-temperature steam injection in prior to the spray injection. The test case with a reduced heat transfer on the passive heat sink showed a faster increase of the P/T inside the containment. The effect of the steam flow direction was also investigated with respect to a multi-dimensional distribution of the local heat transfer on the passive heat sink. The integral effect test data obtained in this study will contribute to validating the evaluation methodology for mass and energy (M/E) and P/T transient of the containment.

• 대한설비관리학회지
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• 제23권4호
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• pp.29-38
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• 2018

Through process quality information, the time required for process quality analysis has been drastically shortened, the process defect rate has been reduced, and the manufacturing lead time has been shortened and the on-time delivery rate has been improved. Therefore, The purpose of this study is to develop a quality information analysis system model that effectively shortens the time required for process quality analysis in automobile safety belt parts manufacturing process. As a result of experiments on communication operation between manufacturing execution system (MES) quality server, injection machine control computer, injection machine programmable logic controller (PLC) and terminal, in analyzing quality information, the conventional handwriting input method took an average of 20 minutes, but the new multi-network method took about 2 minutes on average. In addition, the process defect rate was reduced by 13% and the manufacturing lead time was shortened from 28 hours to 20 hours. The delivery compliance rate improved from 96 to 99%.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.167-168
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• 2004

• 해양환경안전학회지
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• 제18권4호
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• pp.360-364
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• 2012

전기추진시스템 분야에서 AC/DC 컨버터는 상대적으로 간단한 다이오드 소자를 이용하는 정류기가 가장 널리 사용되고 있으며 이 정류기는 입력 전류에 큰 고조파를 포함하고 있어서 고조파 저감을 위한 많은 연구가 진행되고 있다. 본 연구에서 제안된 방식은 다이오드 정류기의 출력 전류를 정류기와 추진전동기 입력측에 주입하여 정류기와 추진전동기 입력 전류에 포함되는 고조파 성분을 줄이고 또한, 와이-델타 변압기를 정류기 및 추진전동기 입력회로에 설치되는 전류주입장치의 분배회로에 사용하여 주입전류와 전원 및 부하를 서로 절연함으로써 전류파형 개선과 전기적 안전성을 확보하였다. 제안한 방법을 현재 사용 중인 전기추진선박에서 적용하여 시뮬레이션 하였으며 기존의 전력변환장치와 비교하여 그 타당성을 입증하였다.

• Nuclear Engineering and Technology
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• 제44권7호
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• pp.709-718
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• 2012

The pressurized water reactor APR1400 adopts DVI (Direct Vessel Injection) for the emergency cooling water in the upper downcomer annulus. The International Standard Problem number 50 (ISP-50) was launched with the aim to investigate thermal hydraulic phenomena during a 50% DVI line break scenario with best estimate codes making use of the experimental data available from the ATLAS facility located at KAERI. The present work describes the calculation results obtained for the ISP-50 using the RELAP5/MOD3.3 system code. The work aims at validation and assessment of the code to reproduce the observed phenomena and investigate about its limitations to predict complicated mixing phenomena between the subcooled emergency cooling water and the two-phase flow in the downcomer. The obtained results show that the overall trends of the main test variables are well reproduced by the calculations. In particular, the pressure in the primary system show excellent agreement with the experiment. The loop seal clearance phenomenon was observed in the calculation and it was found to have an important influence on the transient progression. Moreover, the collapsed water levels in the core are accurately reproduced in the simulations. However, the drop in the downcomer level before the activation of the DVI from safety injection tanks was underestimated due to multi-dimensional phenomena in the downcomer that are not properly captured by one-dimensional simulations.

• 한국유체기계학회 논문집
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• 제17권6호
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• pp.104-108
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• 2014

The recent Fukushima nuclear power plant accidents shows that the core make up at high RCS pressure condition is very important to prevent core melting. The core make up flow at high pressure condition should be driven by gravity force or passive forces because the AC-powered safety features are not available during a Station Black Out (SBO) accident. The reactor Coolant System (RCS) mass inventory is continuously decreased by releasing steam through the pressurizer safety valves after reactor trip during a SBO accident. The core will be melted down within 2~3 hours without core make up action by active or passive mode. In the new design concept of a Hybrid Safety Injection Tank (Hybrid SIT) both for low and high RCS pressure conditions, the low pressure nitrogen gas serves as a charging pressure for a LBLOCA injection mode, while the PZR high pressure steam provides an equalizing pressure for a high pressure injection mode such as a SBO accident. After the pressure equalizing process by battery driven initiation valve at a high pressure SBO condition, the Hybrid SIT injection water will be passively injected into the reactor downcomer by gravity head. The SBO simulation by MARS code show that the core makeup injection flow through the Hybrid SIT continued up to the SIT empty condition, and the core heatup is delayed as much.

• Nuclear Engineering and Technology
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• 제20권1호
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• pp.47-53
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• 1988

본 연구의 목적은 충전/안전주입 펌프 최소순환관으로부터 안전주입신호(s-신호)를제거 함에 따른 원자력 5,6,7,8호기의 고압안전주입계통(HHSIS)의 신뢰도를 분석, 평가하는 것이다. 계산은 s-신호를 제거한 경우와 제거하지 않은 경우에 대하여 각각 수행되었다. 각 경우에 대하여 s-신호 발생시 고압안전주입계통의 이용불능도와 충전/안전주입 펌프의 파손확률이 계산되었다. 계산결과에 따르면, s-신호를 제거함에 따라 고압안전주입계통의 이용불능도는 미세하게 증가하였으며 반면에 충전/안전주입 펌프의 파손확률은 크게 감소하였다. 따라서 여러가지 측면에서 충전/안전주입 펌프의 최소순환관으로부터 s-신호를 제거하고 운전하는 것이 합당하다는 것이 밝혀졌으며, 고압안전주입계통의 이용불능도를 줄이기 위하여 운전절차를 개선하고 운전원의 훈련 및 교육을 강화할 것을 추천한다.

• 한국철도학회:학술대회논문집
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• 한국철도학회 2007년도 춘계학술대회 논문집
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• pp.1016-1022
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• 2007

It is demanded to produce the safety evidence documents in other to approval safety characteristic of railway signaling system which stands is included, it is demanding from IEC 62425 standards. Also it is express clearly that safety assessment if signaling system has to be verification of these safety evidence documents. This Safety Case has the results of safety activity through system life-cycle, such as hazard lists, hazard identification and analysis, risk assessment and countermeasure, verification and test results. Consequently, first of all, the analysis and verification of these Safety Case documents has to be accomplished to approval and acceptance of signaling system safety. And also if the safety assessor was want, it is able to be experimental test auditory which is, arbitrary faults injection test, to above described documents verification. In this paper, the contents and architecture of Safety Case are presented as first steps of safety assessment technology establishment for railway signaling system.

• 한국해양공학회지
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• 제27권2호
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• pp.47-52
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• 2013

A subsea chemical injection system treats blockage problems in a subsea production system. It is important to treat problems quickly, because production delays cause fatal profit losses in a subsea production system. Therefore, the subsea industry requires a relatively higher reliability level for a production system compared to other industries. In this study, a subsea chemical injection system (linked to a control system) to inject chemicals into a subsea X-mas tree was analyzed. By using FSA (Formal Safety Assessment), the risk factors were defined and a quantitative risk analysis utilizing FTA (Fault Tree Analysis) and ETA (Event Tree Analysis) was performed. As a result, the effectiveness of a risk reduction option was evaluated.