• Nuclear Engineering and Technology
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• 제48권2호
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• pp.545-553
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• 2016

The failure probabilities of the reactor pressure vessel (RPV) for low temperature over-pressurization (LTOP) and cool-down transients are calculated in this study. For the cool-down transient, a pressure-temperature limit curve is generated in accordance with Section XI, Appendix G of the American Society of Mechanical Engineers (ASME) code, from which safety margin factors are deliberately removed for the probabilistic fracture mechanics analysis. Then, sensitivity analyses are conducted to understand the effects of some input parameters. For the LTOP transient, the failure of the RPV mostly occurs during the period of the abrupt pressure rise. For the cool-down transient, the decrease of the fracture toughness with temperature and time plays a main role in RPV failure at the end of the cool-down process. As expected, the failure probability increases with increasing fluence, Cu and Ni contents, and initial reference temperature-nil ductility transition ($RT_{NDT}$). The effect of warm prestressing on the vessel failure probability for LTOP is not significant because most of the failures happen before the stress intensity factor reaches the peak value while its effect reduces the failure probability by more than one order of magnitude for the cool-down transient.

• 한국안전학회지
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• 제27권6호
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• pp.192-204
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• 2012

For a severe accident of nuclear power plant, an approach to estimation of the radiological source term using a severe accident code(MELCOR) has been proposed. Although the MELCOR code has a capability to estimate the radiological source term, it has been hardly utilized for the radiological consequence analysis mainly due to a lack of understanding on the relevant function employed in MELCOR and severe accident phenomena. In order to estimate the severe accident source term to be linked with the radiological consequence analysis, this study proposes 4-step procedure: (1) selection of plant condition leading to a severe accident(i.e., accident sequence), (2) analysis of the relevant severe accident code, (3) investigation of the code analysis results and post-processing, and (4) generation of radiological source term information for the consequence analysis. The feasibility study of the present approach to an early containment failure sequence caused by a fast station blackout(SBO) of a reference plant (OPR-1000), showed that while the MELCOR code has an integrated capability for severe accident and source term analysis, it has a large degree of uncertainty in quantifying the radiological source term. Key insights obtained from the present study were: (1) key parameters employed in a typical code for the consequence analysis(i.e., MACCS) could be generated by MELCOR code; (2) the MELOCR code simulation for an assessment of the selected accident sequence has a large degree of uncertainty in determining the accident scenario and severe accident phenomena; and (3) the generation of source term information for the consequence analysis relies on an expert opinion in both areas of severe accident analysis and consequence analysis. Nevertheless, the MELCOR code had a great advantage in estimating the radiological source term such as reflection of the current state of art in the area of severe accident and radiological source term.

• 한국지반공학회:학술대회논문집
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• 한국지반공학회 2002년도 봄 학술발표회 논문집
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• pp.651-656
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• 2002

In general, the most important problem in slope stability analysis is that there is no definite way to describe the natural three-dimensional Joint network. Therefore, the many approaches were tried to anlayze the slope stability. Numerical modeling approach is one of the branch to resolve the complexity of natural system. UDEC, FLAC, and SWEDGE are widely used commercial code for the purpose on stability analysis. For the purpose on the more appropriate application of these kind of code, however, three-dimensional distribution of joint network must be identified in more explicit way. Remaining problem is to definitely describe the three dimensional network of joint and bedding, but it is almost impossible in practical sense. Three dimensional joint generation method with random number generation and the results of generation to UDEC have been applied to settle the refered problems in field site. However, this approach also has a important problem, and it is that joint network is generated only once. This problem lead to the limitation on the application to field case, in practical sense. To get rid of this limitation, Monte Carlo Simulation is proposed in this study 1) statistical analysis of input values and definition of the applied system with statistical parameter, 2) instead of the consideration of generated network as a real system, generated system is just taken as one reliable system, 3) present the design parameters, through the statistical analysis of ouput values Results of this study are not only the probability of failure, but also area of failure block, shear strength, normal strength and failure pattern, and all of these results are described in statistical parameters. The results of this study, shear strength, failure area, pattern etc, can provide the direct basement on the design, cutoff angle, support pattern, support strength and etc.

• 한국통신학회논문지
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• 제29권8C호
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• pp.1034-1039
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• 2004

저장 장치의 고밀도화로 인한 인접 심벌간의 간섭 현상은 연속되는 천이 길이에 의해 가장 큰 영향을 받게 된다. 따라서, 본 논문에서는 천이 회수를 2, k-구속조건을 8로 제한한 새로운 MTR 변조 코드를 제안하였다. 이 코드에 대해 수직 자기기록 장치에서 저주파 대역에 존재하는 매체 잡음으로 인한 성능 감소를 방지하기 위해서 GS(Guided Scrambling) 방법을 이용한 DC-억압을 수행하였다. 또한, 기존의 자기기록 채널에서 사용되던 코드율 8/9인 코드와의 검출 성능을 컴퓨터 모의 실험을 통해 비교 분석하였다.

• 한국기계가공학회지
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• 제17권4호
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• pp.150-159
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• 2018

The present research deals with a finite element analysis and fatigue evaluation of a steam separator of a high-pressure evaporator for the Heat Recovery Steam Generator (HRSG). The fatigue during the expected life of the HRSG was evaluated according to the ASME Boiler and Pressure Vessel Code Section VIII Division 2 (ASME Code). First, based on the eight transient operating conditions prescribed for the HRSG, temperature distribution of the steam separator was analyzed by a transient thermal analysis. Results of the thermal analysis were used as a thermal load for the structural analysis and used to determine the mean cycle temperature. Next, a structural analysis for the transient conditions was carried out with the thermal load, steam pressure, and nozzle load. The maximum stress location was found to be the riser nozzle bore, and hence fatigue was evaluated at that location, as per ASME Code. As a result, the cumulative usage factor was calculated as 0.00072 (much less than 1). In conclusion, the steam separator was found to be safe from fatigue failure during the expected life.

• Composites Research
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• 제32권5호
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• pp.258-264
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• 2019

본 논문에서는 Hashin 파손 기준식과 crack band 모델이 접목된 손상변수를 이용하여 점진적파손해석 방법이 개발되었다. 파손기준식을 이용하여 파손의 개시 유무가 판단된다. 파손이 개시된 경우에는 각 파손모드(섬유 인장/압축, 기지 인장/압축)에서 손상변수가 선형 열화 거동에 따라 계산되고, 손상강성행렬을 계산하는데 사용된다. 손상강성행렬은 손상된 재료에 반영되고, 계산된 손상강성행렬을 이용하여 재료의 완전한 파괴를 의미하는 손상변수가 1인 시점이 되기까지 점진적 파손해석이 계속해서 반복적으로 수행된다. 일련의 과정들은 상용해석프로그램인 ABAQUS에 사용자 정의 부프로그램을 이용하여 수행되었다. 제안된 점진적파손해석 도구의 검증을 위하여, 원공을 가진 복합재료 적층판의 시험 결과와 비교를 수행하였으며, 시험 중 디지털 이미지 상관법을 이용하여 획득한 변형률 거동과 해석을 통해 획득한 변형률 거동을 비교하였다. 제안된 해석결과는 시험 결과와 비교하여 유효한 일치를 보였다.

• 콘크리트학회논문집
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• 제15권5호
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• pp.689-696
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• 2003

최근 ACI 318-02기준 부록 A에 깊은 보의 전단설계에 있어 스트럿-타이 모델을 적용 가능하도록 소개하고 있다. STM은 깊은 보, 개구부가 있는 깊은 보, 코벨, 턱이진 보와 같이 부재의 변형률 분포가 상당히 비선형인 콘크리트 부재의 설계에 광범위하게 사용되고 있다. 본 연구는 고강도콘크리트를 적용한 깊은 보의 각국의 전단강도규준과 전단거동을 평가하고자 실험적 연구로 2점 단순 집중하중을 받는 고강도 RC 깊은 보 5개를 제작하여 파괴 실험을 실시하였다. 또한, 국내 B사의 기계적 정착철물을 사용하여 주인장철근의 양단부에 기계적정착을 적용하였다. 파괴 시 모든 시험체는 가력점과 지지점을 연결하는 주 경사균열이 나타났고, 주인장철근을 기계적 정착한 시험체가 90도 표준갈고리 시험체보다 파괴 시 하중 수행능력이 우수한 것으로 나타났다. 실험결과를 기초로 ACI 318-99 기준, ACI 318-02 부록 A STM, CSA 23.3-94 기준 및 CIRIA Guide-2의 전단설계기준을 비교 평가하였다. ACI 318-99 기준과 ACI 318-02 기준의 스트럿-타이 모델, CIRIA Guide-2는 단순스팬 깊은 보의 극한전단강도 예측 있어 10∼36%정도 낮게 안정적으로 평가하는 것으로 나타났다. ACI 318-99 기준에 의한 전단강도예측값이 표준편차가 가장 낮은 것으로 조사되었다.

• 대한조선학회 특별논문집
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• 대한조선학회 2017년도 특별논문집
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• pp.19-27
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• 2017

In spite of adoption of Intact Stability Code Part A as mandatory, the accidents have been occurred frequently caused by dynamic stability. Therefore International Maritime Organization (IMO) is revising the Intact Stability Code to prevent the cause of accidents. The result of 4th meeting of Sub-committee on Ship Design and Construction (SDC), five mode of the cause was defined and establishing each draft regulations. We consider physical background, mathematical description, draft regulations for five failure mode and sample calculations for ships built by STX Offshore & Shipbuilding.

• 한국콘크리트학회:학술대회논문집
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• 한국콘크리트학회 2003년도 가을 학술발표회 논문집
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• pp.409-412
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• 2003

ACI design code is not capable of evaluating the inter-effects between concrete and torsional reinforcement on the torsional resistance of the reinforced concrete beams. In this study, the failure strengths of the ten reinforced concrete beams subjected to pure torsion were evaluated using 3-dimensional strut-tie models. The analysis results obtained from the present study were compared with those obtained from the ACI design code. The comparison showed that the accuracy and performance of the present method were better than the ACI design code. Thus, the method implementing a 3-dimensional strut-tie model can be possibly applied to the analysis and design of the reinforced concrete beams subjected to pure torsion as a rational design method.

• 대한기계학회논문집A
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• 제27권3호
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• pp.409-415
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• 2003

The purpose of this paper is to develop the 2-Dim Lagrangian Hydrocode for the analysis of large deformations of solids with implementation of the contact algorithm. First, th e governing equations are discretized into a system of algebraic equations. For more accurate and robust contact force computation. the defense node contact algorithm was adopted and implemented. For the verification of the code developed, two cases are carried out; the Taylor-Impact test and two bodies impact. The von -Mises criterion is implemented into the code with the Shock equation of state. The simulation results show a good agreement compared with the published experimental data and results from the commercial code. It is necessary to implement several material models and failure models for applications to different impact and penetration problems.