• Nuclear Engineering and Technology
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• 제40권1호
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• pp.37-48
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• 2008

Flow fields inside feeder pipes have been simulated numerically using a CFD (computational fluid dynamics) code to calculate the shear stress distribution, which is the most important factor in predicting the local regions of feeder pipes highly susceptible to FAC (flow-accelerated corrosion)-induced wall thinning. The CFD approach, with schemes used in this study, to simulate the flow situations inside the CANDU feeder pipes has been verified as it showed a good agreement between the investigation results for the failed feedwater pipe at Surry unit 2 plant in the U.S. and the CFD calculation. Sensitivity studies of the three geometrical parameters, such as angle of the first and second bends, length of the first span between the grayloc hub and the first bend, and length of the second span between the first and the second bends have been performed. CFD analysis reveals that the local regions of feeder pipes of Wolsung unit 1 in Korea, on which wall thickness measurements have been performed so far, are not coincident with the worst regions predicted by the present CFD analysis located in the connection region of straight and bend pipe near the inlet part of the bend intrados. Finally, based on the results of the present CFD analysis, a guide to the selection of the weakest local positions where the measurement of wall thickness should be performed with higher priority has been provided.

• Nuclear Engineering and Technology
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• 제51권5호
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• pp.1470-1476
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• 2019

The nuclear power plants in South Korea have been designed in accordance with the U.S. Regulatory Guide 1.60 (R.G 1.60) design spectrum of which the peak frequency range is 2-10 Hz. The characteristics of the earthquakes at the Korea nuclear power plant sites were observed to be closer to that of Central and Eastern United States (CEUS) than the R.G 1.60, which is a lower amplification in a low frequency range, and a higher amplification in a high frequency range. The possibility of failure for sensitive power plant components in the high frequency range has been considered and evaluated. In this study, in order to improve the reliability of nuclear plant and administrative control procedures, seismic tests of an emergency diesel generator (EDG) were conducted using a shaking table under both high and low frequency ranges. From the tests, oil/lubricant leaks from the bolt connections, the fuel filter and the fuel inlet were observed. Therefore, the check list of nuclear plant components after an earthquake should include bolt connections of EDG as well as anchor bolts.

• International Journal of Computer Science & Network Security
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• 제22권1호
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• pp.225-233
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• 2022

The recent outbreak of corona virus (COVID-19) infectious disease had made its forecasting critical cornerstones in most scientific studies. This study adopts a machine learning based time series model - Auto Regressive Integrated Moving Average (ARIMA) model to forecast COVID-19 confirmed cases in Botswana over 60 days period. Findings of the study show that COVID-19 confirmed cases in Botswana are steadily rising in a steep upward trend with random fluctuations. This trend can also be described effectively using an additive model when scrutinized in Seasonal Trend Decomposition method by Loess. In selecting the best fit ARIMA model, a Grid Search Algorithm was developed with python language and was used to optimize an Akaike Information Criterion (AIC) metric. The best fit ARIMA model was determined at ARIMA (5, 1, 1), which depicted the least AIC score of 3885.091. Results of the study proved that ARIMA model can be useful in generating reliable and volatile forecasts that can used to guide on understanding of the future spread of infectious diseases or pandemics. Most significantly, findings of the study are expected to raise social awareness to disease monitoring institutions and government regulatory bodies where it can be used to support strategic health decisions and initiate policy improvement for better management of the COVID-19 pandemic.

• Nuclear Engineering and Technology
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• 제53권6호
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• pp.2038-2045
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• 2021

The main objective of this work is to propose a reliable routine standard operation procedures (SOP) for structural health monitoring and diagnosis of nuclear power plants (NPPs). At present, NPPs have monitoring systems that can be used to obtain the quantitative health record of containment (CTMT) buildings through system identification technology. However, because the measurement signals are often interfered with by noise, the identification results may introduce erroneous conclusions if the measured data is directly adopted. Therefore, this paper recommends the SOP for signal screening and the required identification procedures to identify the dynamic characteristics of the CTMT of NPPs. In the SOP, three recommend methods are proposed including the Recursive Least Squares (RLS), the Observer Kalman Filter Identification/Eigensystem Realization Algorithm (OKID/ERA), and the Frequency Response Function (FRF). The identification results can be verified by comparing the results of different methods. Finally, a preliminary CTMT healthy record can be established based on the limited number of earthquake records. It can be served as the quantitative reference to expedite the restart procedure. If the fundamental frequency of the CTMT drops significantly after the Operating Basis Earthquake and Safe Shutdown Earthquake (OBE/SSE), it means that the restart actions suggested by the regulatory guide should be taken in place immediately.

• Nuclear Engineering and Technology
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• 제55권9호
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• pp.3493-3505
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• 2023

Reactor containment buildings serve as the last barrier to prevent radioactive leakage due to accidents and their safety is crucial in overpressurization conditions. Thus, the Regulatory Guide (RG) 1.216 has mentioned the global strain as one of failure criteria in the free-field for cylindrical prestressed concrete containment vessels (PCCV) subject to internal pressure. However, there is a limit that RG 1.216 shows the free-field without the specific locations of failure criteria and also the global strain corresponding to only azimuth 135° has been mentioned in NUREG/CR-6685, regardless of the elevations of the structure. Therefore, in order to reevaluate the failure criteria of the 1:4 scaled PCCV, the high fidelity simulation model based on the experimental test was significantly validated in this study, and it was interesting to find that the experimental and numerical result was very close to each other. In addition, for the consideration of the material uncertainties, the Latin hypercube method was used as a statistical approach. Consequently, it was revealed that the radial displacements of various azimuth area such as 120°, 135°, 150°, 180° and 210° at elevations 4680 mm and 6,200 mm can represent as the global deformation at the free-field, obtained from the statistical approach.

• 융합경영연구
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• 제5권1호
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• pp.1-20
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• 2017

An increasing number of researchers are finding that 'poor' CG is a leading factor in dismal performance, manipulated financial reports, and unhappy stakeholders. Undoubtedly, qualified, trained and mature Chartered Forensic Accountants (CFA's) can prove to be a valuable asset to the corporate sector, and gradually help to improve their CG system. The fundamental objective of this study is to find out "how can we integrate the expertise of the FA to improve the overall CG scenario prevalent in India?" This is a preliminary investigation of the necessary skills, educational and training requirements for CFA's to improve CG system. During 2011-12, a questionnaire-based survey was conducted in the NCR of India using a sample size of 120 practicing chartered accountants, accounting academics, and potential users of FA services. Results indicate that potential practitioners, academics and users agree that "critical thinking, written & oral communication, legal knowledge, auditing skills, deductive analysis, investigative flexibility, analytical proficiency and unstructured problem-solving are the most important skills required for the CFAs." Moreover, we found that all of the skills investigated in this study are 'potentially' important for the CFAs, which the educators at the Universities should use as an overall guide while designing their FA curriculum."

• 산경연구논집
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• 제15권6호
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• pp.25-32
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• 2024

Purpose: This research explores to (1) identify the leading challenges that the beauty care industry faces currently, which includes sustainable development, ethics, and industry laws, (2) describe how these challenges impact industries' practices and customer experience, and (3) propose plausible strategies to address these issues in an effort to enhance sustainability, ethical business practices, and compliance with legal norms in the beauty care industry. Research design, data and methodology: The research approach used is the systematic literature review approach to identify the relevant literature that addresses the current challenges in the beauty care industry and to assess the results of prior studies. Results: The finding indicated the following solutions to handle the current issues in the beauty industry: Solution to (1) Environmental Impact: Sustainable Production and Packaging, (2) Ethical Concerns: Enhancing Supply Chain Transparency, (3) Regulatory Challenges: Proactive Compliance and International Standardization, and (4) Technological Challenges: Personalization and Digital Engagement. Conclusion: Based on the conclusions made in the findings' section, this research examines the implications of the solutions to provide an insight into how the strategies can guide future practices in the beauty care industry. It also points out how these insights can be applied by industry practitioners to improve sector operational and strategic performance.

• 방사성폐기물학회지
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• 제8권4호
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• pp.311-318
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• 2010

공학적 안전설비 공기정화계통의 규제지침인 Reg. Guide 1.52(Rev.3)의 변경사항중 성능시험과 관련한 운전가능성 시험시간 단축, HEPA 필터 현장누설시험용 시험물질 변경 및 활성탄 성능시험 Methyl Iodidie 투과허용율 상향 변경을 영광 5,6호기에 적용하고자, 모사실험장치와 현장 설비를 활용하여 기술적 타당성을 확인하는 실험을 수행하였다. 10시간 이상의 장시간 운전가능성 시험을 통해 계통내 습분을 제거하여도 시험후 1~4일만에 회복됨을 확인하여 운전가능성 시험은 기기적 운전가능성 점검에 적합한 매월 15분 이상의 시험을 수행하는 것이 타당함을 확인하였다. HEPA 필터 현장누설시험용 시험물질 변경을 위해 DOP와 PAO의 에어로졸 입자크기, 발생량, 누설인지도를 비교한 결과 PAO는 원전에서도 DOP 대체시험물질로 사용 가능함을 확인하였다. 베드깊이 4 인치 이상의 활성탄여과기에 대한 Methyl Iodide의 투과율 허용치가 0.175 %에서 0.5 %로 상향 변경된 것은, ASTM D3803(1989)으로의 활성탄 성능시험 방법 변경에 따른 것으로서, $30^{\circ}C$ 상대습도 95 %에서의 Methyl Iodide 투과허용율 0.5 %가 사용 중 활성탄의 성능을 시험하기에 충분히 보수적인 시험방법임을 확인하였다. 본 실험 결과를 바탕으로 영광 5,6호기는 인허가변경을 완료하였다.

• 대한토목학회논문집
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• 제5권2호
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• pp.91-99
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• 1985

원자력(原子力) 구조물(構造物)의 내진해석(耐震解析)에 사용(使用)되어온 입력운동(入力運動)의 가속도 크기와 지속시간(持續時間)을 조사(調査)하였다. 그 중 수치화(數値化)된 자료를 얻을 수 있었던 지속시간(持續時間) 24초(秒)인 두 개의 인공가속도(人工加速度)-시간이력곡선(時間履歷曲線)에 대하여 가속도응답(加速度應答)스펙트럼과 스펙트럼강도(强度)를 계산하여 특성(特性)을 파악하고, 지속시간(持續時間) 이외의 다른 특성(特性)이 크게 다르지 않도록 가속도(加速度) 곡선(曲線) 하나를 개선(改善)시켜 지속시간 15초(秒)의 다른 인공가속도(人工加速度)-시간이력곡선(時間履歷曲線)을 만들었다. 24초(秒)의 두 곡선(曲線)과 개선(改善)시킨 곡선(曲線)을 각각 원자력(原子力) 5, 6호계(號繼) 부품냉각건물(部品冷却建物)의 모델에 입력(入力)시켜 지진해석(地震解析)을 수행(遂行)하였다. 24초(秒)의 원(原) 곡선(曲線)과 이로부터 개선(改善)시킨 곡선(曲線)을 사용(使用)한 결과(結果)는 거의 동일(同一)하였으나, 24초(秒) 두 곡선(曲線) 사용(使用)한 결과(結果)는 그 경향(傾向)은 같으나 큰 차이(差異) 보였다. 또한 본(本) 연구(硏究)에서 사용(使用)한 모델에 개선(改善)시킨 곡선(曲線)의 사용(使用)이 컴퓨터 이용시간(利用時間)을 약 절반으로 줄일 수 있음을 알았다.

• 한국화재소방학회논문지
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• 제34권3호
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• pp.134-140
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• 2020

국내 원전은 심층화재방어 개념에 따라 화재 발생 시 원전 외부로 방사능의 누출을 억제하고 발전소의 안전정지기능이 유지되어야 한다. 또한 화재방호 설비가 노형별 화재방호 설계 요건에 맞게 설치되어 운전 중 요구하는 설계기능이 유지되고 있는지 관련 규정에 따라 정기적인 시험으로 건전성을 확인한다. 현재 국내 원전은 원자력안전법과 국내외 소방관계법을 동시에 적용하고 있으며 특히 이러한 법규 환경과 더불어 2017년 국내 최초 영구 정지된 고리1호기에도 유사한 규정이 적용될 것으로 사료된다. 하지만 향후 단계적인 해체원전의 증가를 고려하여 해체특성을 고려한 화재방호 세부 규제규정이 마련되어 체계적으로 해체원전의 화재방호프로그램이 정착되는 기반을 마련할 필요가 있다. 따라서 원전을 다수 운영 중인 미국, 일본, 캐나다 및 유럽 국가들의 원자력 법령체계를 검토하였고, 해외 해체 원전에 활용되고 있는 미국 영구정지 및 해체원전의 화재방호 규제지침인 Reg Guide 1.191의 규제 요건을 고려한 해체원전의 화재방호프로그램 법령체계 마련을 위한 방향을 제시하였다. 본 연구에서는 해체원전의 화재방호프로그램 최적화 및 화재분야의 원전 해체 기반기술 확보를 위해 화재방호 규정 마련을 위한 방향을 제시하고자 한다.