• 전기학회논문지P
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• 제64권4호
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• pp.220-230
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• 2015

Rolling stock RAMS is a field of engineering which integrates reliability, availability, maintainability and safety (RAMS) characteristics into an inherent product design property through rolling stock system engineering process. It is implemented to achieve operational objectives successfully, and recently the RAMS has become a rapidly growing engineering discipline because it has a great potential to ensure safety and improve cost effectiveness. However, the Korean rolling stock industry has not yet implemented RAMS management in the rolling stock engineering process, despite the issue having been addressed since the introduction of the KTX. Thus, this paper discusses the processes, methods and techniques for RAMS assessment in three parts. Firstly, it outlines a process of the overall RAMS performance assessment for achieving technical RAMS design criteria. Secondly, it discusses a process for assessing the operational RAM and allocating the RAM. This paper also proposes a model for assessing safety-based risk management, which includes five analytic techniques for identifying the causes and consequences of a system failure. Finally, a case example is provided for the risk assessment of the pneumatic braking device.

• Structural Engineering and Mechanics
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• 제36권3호
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• pp.301-319
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• 2010

The paper seeks to explore some aspects of the current state of knowledge on progressive collapse in the technical literature covering blast loads and structural analysis procedure applicable to reinforced concrete (RC) buildings. The paper describes the progressive collapse analysis of a commercial RC building located in the city of Riyadh and subjected to different blast scenarios. A 3-D finite element model of the structure was created using LS-DYNA, which uses explicit time integration algorithms for solution. Blast loads were treated as dynamic pressure-time history curves applied to the exterior elements. The inherent shortcomings of notional member removal have been taken care of in the present paper by simulating the damage of structural elements through the use of solid elements with the provision of element erosion. Effects of erosion and cratering are studied for different scenarios of the blast.

• Nuclear Engineering and Technology
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• 제41권3호
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• pp.307-318
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• 2009

KAERI (Korea Atomic Energy Research Institute) has developed the GAMMA+ code for a thermo-fluid and safety analysis of a VHTR (Very High Temperature Gas-Cooled Reactor). A key safety issue of the VHTR design is to demonstrate its inherent safety features for an automatic reactor power trip and power stabilization during an anticipated transient without scram (ATWS) accident such as a loss of forced cooling by a trip of the helium circulator (LOFC) or a reactivity insertion by a control rod withdrawal (CRW). This paper intends to show the ATWS assessment capability of the GAMMA+ code which can simulate the reactor power response by solving the point-kinetic equations with six-group delayed neutrons, by considering the reactivity changes due to the effects of a core temperature variation, xenon transients, and reactivity insertions. The present benchmark calculations are performed by using the safety demonstration experiments of the 10 MW high temperature gas cooled-test module (HTR-10) in China. The calculation results of the power response transients and the solid core temperature behavior are compared with the experimental data of a LOFC ATWS test and two CRW ATWS tests by using a 1mk-control rod and a 5mk-control rod, respectively. The GAMMA+ code predicts the power response transients very well for the LOFC and CRW ATWS tests in HTR-10.

• 전기학회논문지
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• 제57권12호
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• pp.2220-2227
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• 2008

The safety equipments of railway level crossing which are installed at intersections between roads and railway lines prevent level crossing accidents by informing all of the vehicles and pedestrians of approaching trains. The intelligent safety system for level crossing which employs information and communication technology has been developed in USA and Japan, etc. But, in Korea, the relevant research has not been performed. In this paper, we analyze the cause of railway level crossing accidents and the inherent problem of the existing safety equipments. Based on analyzed results, we design the intelligent safety system which prevent collision between a train and a vehicle. This system displays train approaching information in real-time at roadside warning devices, informs approaching train of the detected obstacle in crossing areas, and is interconnected with traffic signal to empty the crossing area before train comes. Especially, we present the video based obstacle detection algorithm and verify its performance with prototype H/W since the abrupt obstacles in crossing areas are the main cause of level crossing accidents. We identify that the presented scheme detects both pedestrian and vehicle with good performance.

• 시스템엔지니어링학술지
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• 제19권2호
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• pp.46-58
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• 2023

Deterministic safety analysis is a crucial part of safety assessment, particularly when it comes to demonstrating the safety of nuclear power plant designs. The traditional approach to deterministic safety analysis models is to model the nuclear core using point kinetics. However, this simplified approach does not fully reflect the real core behavior with proper moderator and fuel reactivity feedbacks during the transient. The use of Multi-Physics approach allows more precise simulation reflecting the inherent three-dimensionality (3D) of the problem by representing the detailed 3D core, with instantaneous updates of feedback mechanisms due to changes of important reactivity parameters like fuel temperature coefficient (FTC) and moderator temperature coefficient (MTC). This paper addresses a CEA ejection accident at hot full power (HFP), in which the underlying strong and un-symmetric feedback between thermal-hydraulics and reactor kinetics exist. For this purpose, a multi-physics analysis tool has been selected with the nodal kinetics code, 3DKIN, implicitly coupled to the thermal-hydraulic code, RELAP5, for real-time communication and data exchange. This coupled approach enables high fidelity three-dimensional simulation and is therefore especially relevant to reactivity initiated accident (RIA) scenarios and power distribution anomalies with strong feedback mechanisms and/or un-symmetrical characteristics as in the CEA ejection accident. The Systems Engineering approach is employed to provide guidance in developing the work in a systematic and efficient fashion.

• 정보처리학회논문지:소프트웨어 및 데이터공학
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• 제2권10호
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• pp.661-668
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• 2013

Safety Critical 시스템은 시스템의 기능적인 실패 또는 예기치 못한 상황의 발생으로 인해 인명피해, 재산피해, 환경 피해와 같은 치명적인 사고를 초래할 수 있는 시스템을 의미한다. 그러므로 Safety Critical 시스템의 안전을 보장하기 위해서는 시스템 설계 단계에서 시스템에 존재할 수 있는 위험성들이 충분히 고려되어야 하며, 사고가 발생했을 시 피해를 최소화시키기 위한 일련의 예방 동작들이 설계되어야 한다. 현재에는 Safety Critical 시스템의 설계 단계에서 위험성을 식별하고 분석하기 위한 많은 방법들이 연구되었으며, 이 중에는 예기치 못한 사건으로 인한 피해를 예방하는 동작들의 성공 여부를 분석하는 기법도 존재한다. 본 연구에서는 위의 예방 동작들의 성공 여부에 대한 분석뿐만 아니라 기존 연구들에서 언급하지 못한 예방 동작들 간의 충돌과 이로 인해 발생할 수 있는 피해를 분석하는 방법을 제시하고자 한다. 제안한 방법을 통해 Safety Critical 시스템의 안전성이 견고해지고 피해 예방을 위한 동작들의 올바른 설계에 도움이 될 수 있을 것이다.

• Korean Chemical Engineering Research
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• 제52권4호
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• pp.467-474
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• 2014

화학공정의 기초설계는 물질수지와 열수지 계산을 기초로 공정의 경제성을 확보하고 주어진 조건 내에서 원하는 제품을 생산 가능하도록 한다. 이 단계를 통해 공정은 사용될 물질과 반응, 설비의 구조와 운전 조건 등이 결정되기 때문에 이후 바뀔 수 없는 고유한 특성을 갖게 된다. 고유한 특성은 뛰어난 경제성일 수도 있지만 다양한 잠재적 위험요인을 내포하는 것일 수도 있다. 따라서 기초설계를 위한 공정모사와 정량적 위험성 평가 기법의 통합을 통해 보다 안전하면서도 경제적인 공정을 설계하는 것이 중요하다. 본 논문에서는 LNG 액화공정을 Aspen HYSYS를 이용하여 모사하고, 폭발 사고에 대한 정량적 위험성 평가를 수행함으로써 잠재적 위험성을 최소화하면서도 경제성을 고려하도록 설계변수를 결정하였다. 이를 위해 확률적 최적화 방법론을 이용하여 Aspen HYSYS의 최적화 한계를 극복하였고, Aspen HYSYS와 Matlab의 연동을 통해 정량적 위험성 평가의 정확성을 높이며 최적화를 용이하게 하였다. 정량적 위험성 평가 결과, 공정 변수 중 안전성 확보를 위해 중요한 변수는 혼합냉매의 압력이었고, 0.5~10%의 운전비용 증가를 통해 잠재적 위험성을 4~18% 줄일 수 있었다. 비용을 크게 증가시킬수록 위험성의 절대적 수치는 낮아지지만 비용 대비 위험성 감소의 효과는 떨어졌다. 이처럼 공정모사와 정량적 위험성 평가 기법의 통합은 태생적으로 보다 안전한 공정의 설계가 가능하게 하고, 기초설계 단계에서부터 공정 내 위험요인을 수치적으로 확인할 수 있어 위험요인이 적은 특성을 갖도록 공정을 설계하는데 도움이 될 것이다.

• 한국지반공학회:학술대회논문집
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• 한국지반공학회 2005년도 지반공학 공동 학술발표회
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• pp.649-654
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• 2005

Shallow slope failures in residual soil during periods of prolonged infiltration are common over the world. One of the key factors that dominate slope stability is hydrological response associated with infiltration. Hence, the soil-water profile during rainfall infiltration into unsaturated soil must me examined to evaluate slope stability. However, the hydraulic response of unsaturated soil is complicated by inherent uncertainties of the soil hydraulic properties. This study presents a methodology for assessing the effects of parameter uncertainty of hydraulic properties on the response of a analytical infiltration model using first-order reliability method. The unsaturated soil properties are considered as uncertain variables with means, standard deviations, and marginal probability distributions. Sensitivities of the probabilistic outcome to the basic uncertainties in the input random variables are provided through importance factors.

• 대한토목학회논문집
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• 제8권3호
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• pp.85-90
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• 1988

균질토 사면에서 파괴에 대한 확률론적모델이 제시되었다. 사면의 안전은 관례적인 안전을 보다는 파괴확률로써 측정된다. 사면파괴의 Safety Margin은 정규분포라 가정하였다. 어떤 균질한 흙층에 있어서 흙의 특성에 영향을 주는 불확실성의 원인은 본래의 공간적인 가변성, 불충분한 시료에서 오는 판단오차 그리고 실험오차등이 었다. 파괴면을 따라 존재하는 전단강도의 불확실성은 1차원 Random Field Madels로 표현되었다. 파괴aus의 양상은 대수나선 곡선을 따른다고 가정하였다. 파괴면과 그것을 따라 작용하는 힘의 통계적 특성을 유도하여 사면의 파괴확률을 계산하였다. 마지막으로 개발된 절차가 사면의 신뢰성 해석에 대한 하나의 예제 연구에 적용되었다.

• Nuclear Engineering and Technology
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• 제51권1호
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• pp.116-124
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• 2019

$M^2LFR-1000$ is a medium-power modular lead-cooled fast reactor, developed by University of Science and Technology of China (USTC), aiming at achieving a reactor design fulfilling the Gen IV nuclear system requirements and meanwhile emphasizing the optimum safety and economics. In order to evaluate the safety performance of $M^2LFR-1000$ reactor core, three typical transients are selected from initiating events, which are unprotected transient overpower (UTOP), unprotected loss of offsite power (ULOHS+ULOF) and increase of feedwater flowrate with primary pumps trip (IFW+PLOF). These three transients presented and discussed in this paper are performed with the code Analysis of THermal-hydraulics of LEaks and Transients (ATHLET), which is developed by Gesellschaft $f{\ddot{u}}r$ Anlagen-und Reaktorsicherheit gGmbH (GRS). The results indicate that the $M^2LFR$ is safe enough under these three transients due to the good inherent safety features of the reactor, without human intervention, the reactor will reach a new steady state under UTOP condition.