• 한국철도학회논문집
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• 제10권5호
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• pp.520-526
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• 2007

본 논문에서는 한국형 틸팅열차의 유지보수 활동을 위해 신뢰성기반유지보수체계를 제안하였다. 열차시스템을 3단계의 교체 부품 단위로 분류하고, 각 단위에 대해 기능블록도를 작성한 후 고장모드 영향 분석을 실시하였다. 각 단위의 심각도를 결정한 후 유지보수 정책을 제안하였으며, 틸팅열차를 위한 유지보수 기준을 정하고, 실제 사례를 제시하였다. 제안된 신뢰성기반유지보수체계는 기존 유지보수 체계와도 호환성을 갖고 있으며, 안전성 향상과 유지보수 활동 효율화에 기여할 수 있다.In this paper, a reliability centered maintenance (RCM) system is proposed to perform maintenance action for Korean Tilting Train. The train system was divided into line replaceable units up to three steps. Functional block diagrams were drawn and failure mode effect analysis for the units was carried out. The criticality of each unit was determined and a maintenance policy was proposed. Maintenance and repair criteria for the tilting train were determined and an example was presented. The proposed RCM system is compatible with the previous maintenance system and contributes to improvement of safety and efficiency of maintenance action.

• Nuclear Engineering and Technology
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• 제46권3호
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• pp.313-342
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• 2014

A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark for Uncertainty Analysis in Modeling (UAM) is defined in order to facilitate the development and validation of available uncertainty analysis and sensitivity analysis methods for best-estimate Light water Reactor (LWR) design and safety calculations. The benchmark has been named the OECD/NEA UAM-LWR benchmark, and has been divided into three phases each of which focuses on a different portion of the uncertainty propagation in LWR multi-physics and multi-scale analysis. Several different reactor cases are modeled at various phases of a reactor calculation. This paper discusses Phase I, known as the "Neutronics Phase", which is devoted mostly to the propagation of nuclear data (cross-section) uncertainty throughout steady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured data are available) are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, and VVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments and the SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility. Analyzed results include the top five neutron-nuclide reactions, which contribute the most to the prediction uncertainty in keff, as well as the uncertainty in key parameters of neutronics analysis such as microscopic and macroscopic cross-sections, six-group decay constants, assembly discontinuity factors, and axial and radial core power distributions. Conclusions are drawn regarding where further studies should be done to reduce uncertainties in key nuclide reaction uncertainties (i.e.: $^{238}U$ radiative capture and inelastic scattering (n, n') as well as the average number of neutrons released per fission event of $^{239}Pu$).

• 방사성폐기물학회지
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• 제4권1호
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• pp.41-50
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• 2006

본 연구에서는 사전연구로부터 사용후핵연료의 처분용기 원형모델로 제안된 처분용기의 전체 크기와 배열을 평가하기 위하여 일련의 공학적 분석을 수행하였다. 그러한 노력의 결과 용기 내부 저장통의 배열형태와 외곽쉘과 상하부 뚜껑의 두께와 같은 새로운 설계변수를 도출하였다. 공학적 분석 작업에는 처분용기의 기계구조 해석 결과를 근거로 도출된 용기의 규격자료에 대한 방사선 안전성 측면에서의 타당성을 검토하기 위하여 방사선차폐 해석과 핵 임계 해석 등이 수행되었다. 처분용기 내부 삽입체의 직경 변화에 따른 구조안정성 해석 결과에 따르면, 직경 102cm 일 때 극한 외압조건은 물론 정상적인 외압조건 하에서도 최대 Von Mises 응력이 안전계수 2.0을 만족하는 것으로 나타났다. 이 경우에서도 핵 임계 및 방사선차폐 해석 결과 안전기준치를 만족시키며, 무게는 20톤 가량 줄어드는 효과가 있는 것으로 나타났다.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2005년도 추계 학술대회 논문집
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• pp.153-162
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• 2005

본 연구에서는 사전연구로부터 사용후 핵연료의 처분용기 원형모델로 제안된 처분용기의 전체 크기와 배열을 평가하기 위하여 일련의 공학적 분석을 수행하였다. 그러한 노력의 결과 용기 내부 저장통의 배열형태와 외곽쉘과 상하부뚜껑의 두께와 같은 새로운 설계변수를 도출하였다. 공학적 분석 작업에는 처분용기의 기계구조 해석 결과를 근거로 도출된 용기의 규격자료에 대한 방사선 안전성 측면에서의 타당성을 검토하기 위하여 방사선차폐 해석과 핵임계 해석 등이 수행되었다. 처분용기 내부 삽입체의 직경변화에 따른 구조안정성 해석 결과에 따르면, 직경 102cm일 때 극한 외압조건은 물론 정상적인 외압조건 하에서도 최대 Von Mises 응력이 안전계수 2.0을 만족하는 것으로 나타났다. 이 경우에도 핵임계 및 방사선차폐 해석 결과 안전기준치를 만족시키며, 무게는 20톤 가량 줄어드는 효과가 있는 것으로 나타났다.

• Journal of Radiation Protection and Research
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• 제41권2호
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• pp.117-121
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• 2016

Background: Definition and grouping of initiating events (IEs) are important basics for probabilistic safety assessment (PSA). An IE in a spent fuel reprocessing plant (SFRP) is an event that probably leads to the release of dangerous material to jeopardize workers, public and environment. The main difference between SFRPs and nuclear power plants (NPPs) is that hazard materials spread diffusely in a SFRP and radioactive material is just one kind of hazard material. Materials and Methods: Since the research on IEs for NPPs is in-depth around the world, there are several general methods to identify IEs: reference of lists in existence, review of experience feedback, qualitative analysis method, and deductive analysis method. While failure mode and effect analysis (FMEA) is an important qualitative analysis method, master logic diagram (MLD) method is the deductive analysis method. IE identification in SFRPs should be consulted with the experience of NPPs, however the differences between SFRPs and NPPs should be considered seriously. Results and Discussion: The plutonium uranium reduction extraction (Purex) process is adopted by the technics in a model reprocessing plant. The first extraction cycle (FEC) is the pivotal process in the Purex process. Whether the FEC can function safely and steadily would directly influence the production process of the whole plant-production quality. Important facilities of the FEC are installed in the equipment cells (ECs). In this work, IEs in the FEC process were identified and categorized by FMEA and MLD two methods, based on the fact that ECs are containments in the plant. Conclusion: The results show that only two ECs in the FEC do not need to be concerned particularly with safety problems, and criticality, fire and red oil explosion are IEs which should be emphatically analyzed. The results are accordant with the references.

• 대한지리학회지
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• 제44권2호
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• pp.187-205
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• 2009

최근 지리학 및 교통 관련 분야에서는 교통 네크워크의 잠재적 손실이 지리 공간상에서 어떠한 영향을 주는가를 살피는 연구가 중요한 주제로 등장하고 있다. 서울의 지하철망은 대규모의 도심 통행을 지지히는 중요한 기반시설이며, 특히 환승역은 그 기능을 상실할 경우 전체 교통망의 신뢰도에 큰 영향을 줄 수 있는 중요한 교통 입지시설이다. 이 논문은 지하철 환승역의 기능 손실이 지하철망의 신뢰도과 대응력에 어떠한 영향을 주는지를 네트워크의 위상학적인 차원, 전체 지리 공간, 그리고 개별 환승역 차원에서 살펴본다. 시뮬레이션을 통한 분석 결과, 서울 지하철망은 상당히 높은수준의 네트워크 신뢰도를 보였으나 환승역 간에는지리적으로 유의미한 변이가 있음을 확인하였다.

• 농촌계획
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• 제18권4호
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• pp.27-34
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• 2012

The purpose of this study is to analyze the community center users' the determinants of utilization & satisfaction for the exploit and to draw out the implication as to what are the influencing factors. The ordered logit model approach was used to examine the determinants. For the use of community center, we surveyed by mail subjecting on rural residents for one month, June 2012, analyzed 625 valid questionnaires. The findings are as follows. First, 'Facility-Satisfaction', 'Education', 'Exploit-Frequency' and 'Age' are the most important factors which affect users' satisfaction. Second, 'A meeting hall function', 'Cultural & Educational function', 'Social & Organizational function', and 'functional criticality function' influence the attributes of users' utilization. Therefore, it is needed to establish the various functions of community center and to prepare the vitalization plan in futuristic viewpoint reflecting the change of rural area. In addition, since there is no clear entity to supervise community center administratively, policy support system to community center should be equipped. Along with these, it is needed to develop managing and operation model for customized community center.

• Nuclear Engineering and Technology
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• 제21권4호
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• pp.245-258
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• 1989

열중성자로의 핵계산을 위한 69군 단면적 라이브러리를 생산하였다. 기본 평가핵자료로는 IAEA Nuclear Data Section에서 수집된 자료가, 그리고 이를 처리하여 군정수화 하는데는 NJOY코드가 이용되었다. 새로이 마련된 라이브러리의 유용성을 검증하기 위해 각기 산화우라늄과 금속 우라늄 연료로 구성된 임계실험치를 WIMS-KAERI 코드로 계산된 결과와 비교, 검토하였다. 총 88임계결과에 대해 평균 $K_{eff}$ 값 0.9997, 그리고 표준 편차 0.69%를 보였다. PWR 연료의 연소결과로 얻어진 우라늄과 플루토늄 생성량에 대한 평가에서도 전반적으로 좋은 결과를 얻었다.다.

• Advances in Automotive Engineering
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• 제1권1호
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• pp.61-77
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• 2018

In this study, the effects of sitting position of the driver on the whiplash neck injury have been analyzed experimentally by using hybrid III series 50 percentile male crash test dummy. A testing platform consisting of vehicle ground, driver foot rest, driver seat and a 3-point seatbelt has been prepared. This testing platform and the instrumented crash test dummy are prepared for tests according to the Euro NCAP whiplash testing protocol. The prepared test set-up has been exposed to 3 different acceleration-time loading curves defined in the Euro NCAP whiplash testing protocol by performing sled tests. 9 different sled tests have been performed with the combinations of 3 different seating positions of the crash test dummy and 3 different acceleration-time loading curves. The sensor data obtained from the crash test dummy and high-speed videos taken are analyzed according to the injury assessments criteria defined in the Euro NCAP whiplash testing protocol and the criticality of the whiplash injury is defined. It is seen that the backset distance of the driver head with the headrest and the height difference of the top of the head of the driver with the headrest have a great importance on whiplash injuries.

• 대한안전경영과학회지
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• 제16권4호
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• pp.11-19
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• 2014

Modern systems development becomes more and more complicated due to the need on the ever-increasing capability of the systems. In addition to the complexity issue, safety concern is also increasing since the malfunctions of the systems under development may result in the accidents in both the test and evaluation phase and the operation phase. Those accidents can cause disastrous damages if explosiveness gets involved therein such as in weapon systems development. The subject of this paper is on how to incorporate safety requirements in the design of safety-critical systems. As an approach, a useful system structure using the method of design structure matrix (DSM) is studied while reflecting the need on systems safety. Specifically, the effects of system components failure are analyzed and numerically modeled first. Also, the system components are identified and their interfaces are represented using a component DSM. Combining the results of the failure analysis and the component DSM leads to a modified DSM. By rearranging the resultant DSM, a modular structure is derived with safety requirements incorporated. As a case study, application of the approach is also discussed in the development of a military UAV plane.