• 시스템엔지니어링학술지
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• 제5권1호
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• pp.33-41
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• 2009

The analog or partly digital typed interface of main control room in nuclear power plant (NPP) is gradually being replaced to the totally digitalized interface suitable for the digital environment. SKN 3,4 Nuclear Power Plant is currently developed in such a way to employ advanced displays and controls such as computerized procedure system(CPS), large display panel(LDP), and Soft control. According to the developed design process, the main control room (MCR) of the SKN3,4 was aesthetically designed based on a design concept of the health and sustainability and technically evaluated with human factors guidelines, which somehow lack of the confidence on the evaluation for the rapidly changing digital environment. The suitable review guideline for the digitalized interface and the environment was developed such as the guideline for CPS with information displays on VDU. For the guideline development, tremendous guidelines and technical papers related to evaluation issues of digital environment has been collected, analyzed and transformed to electric database forms and then built on database management system, called Design Review Supporting System to retrieve the appropriate issues for the practical usage of evaluators-in-field.

• 시스템엔지니어링학술지
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• 제4권2호
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• pp.55-61
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• 2008

In this paper, there is the case study which assesses the systems engineering capability maturity of the safety organization that performs the Railway Safety project using systems engineering method. To In ore effective and efficient a research and development to railway safety domain, a new research and development method can be progressively needed such as systems engineering. To assess quantitatively research of systems engineering efforts in the railway safety project, SECM(EIA/IS 731) Standard is utilized in the paper. It is by questionnaire that the capability maturity assessment is executed wit h the safety organization and staffs who performs the systems engineering activities; requirement analysis and management, interface control management. product verification and validation, and so on. As a result, the systems engineering capability level of the safety organization rises from 0 level at the initial project to 2 level after two years and all staffs give an affirmative answer about the importance and effectiveness of the systems engineering approach.

• 한국항행학회논문지
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• 제15권1호
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• pp.39-53
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• 2011

모바일 장치의 광범위한 응용과 더불어 통신 보안과 연구가 최근 중요한 관심사가 되고 있다. 본 논문에서는 바이오매트릭스의 지문과 음성의 특징을 이용한 모바일 통합 OTP의 일회용 암호 키 토큰을 생성하는 방법을 제안한다. 강력한 개인 인증에 사용되는 바이오매트릭스의 지문과 음성 정보를 이용하여 모바일 환경의 가변적이고 안전한 일회용 암호 키를 생성하는 OTP 프레임워크를 제안하였으며, 또한 제안 기법에 대한 dendrogram을 이용한 지문과 음성 특징 점에 의한 준동형적 가변성 그리고 지문과 음성 특징 점의 분포를 시뮬레이션 하여 유효성을 검증하였다.

• 한국전문물리치료학회지
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• 제25권1호
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• pp.53-61
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• 2018

Background: The process of language translation, adaptation, and cross-cultural validation of tools for use in multiple countries requires the adoption of well-established, comprehensive, and rigorous methodological approaches. Back translation, which is the most recommended method, permits the detection of errors in the translation and the identification of words or phrases that cannot be accurately or literally translated. Objects: The aim of this study was to verify the content validity of a Korean version of a Balance Evaluation Systems test (BESTest) by using a back-translation method. Methods: This research was conducted in six steps: 1) translation of the BESTest into Korean, 2) evaluation of the translation conformity of Korean-translated BESTest, 3) evaluation of the degree of translation comprehension, 4) back translation of Korean BESTest, 5) evaluation of the technical and conceptual equivalence, and 6) completion of the Korean version of BESTest by the translation verification committee. Results: In this study, Korean version of the BESTest achieved a rating of more than 3 (moderate) for translation comprehension, and technical equivalence and conceptual equivalence of back translation were evaluated as 3 (moderate) or more. Conclusion: The Korean version of the BESTest has proven content validity and is an appropriate tool to measure balance function.

• 한국항공우주학회지
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• 제34권4호
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• pp.89-101
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• 2006

본 논문에서는 HAUSAT-2 전력계의 설계와 각 모드별로 에너지 평형 해석을 통한 전력계 설계의 타당성을 검증하였다. 태양전지판은 GaAs 셀을 사용하였고 디지털 방식의 최대 전력 추적기를 채택하였다. 배터리 팩은 4개의 Li-Ion 셀로 구성하였고 최대 전력 추적기와 배터리 충전 조절기로 배터리 충전 기능을 구현하였다. 전력 제어기는 DC-DC 변환기로 요구되는 전압을 출력하고 상용 IC 및 MOSFET으로 이루어진 전력 분배기가 서브시스템 및 탑재체에 전력을 분배시킨다. 전력생성 분석은 다양한 승교점 지방시(LTAN)를 가지는 궤도를 고려하여 수행하였으며, 이 중 HAUSAT-2의 임무 수행에 적합한 궤도를 선정하여 모드별 전력 사항을 반영하여 에너지 평형 해석(EBA)을 진행하였다.

• Nuclear Engineering and Technology
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• 제47권5호
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• pp.596-607
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• 2015

In this paper, we describe a computer program, iBEST (inverse Burnup ESTimator), that we developed to accurately estimate the burnup histories of spent nuclear fuels based on sample measurement data. The burnup history parameters include initial uranium enrichment, burnup, cooling time after discharge from reactor, and reactor type. The program uses algebraic equations derived using the simplified burnup chains of major actinides for initial estimations of burnup and uranium enrichment, and it uses the ORIGEN-S code to correct its initial estimations for improved accuracy. In addition, we newly developed a stable bisection method coupled with ORIGEN-S to correct burnup and enrichment values and implemented it in iBEST in order to fully take advantage of the new capabilities of ORIGEN-S for improving accuracy. The iBEST program was tested using several problems for verification and well-known realistic problems with measurement data from spent fuel samples from the Mihama-3 reactor for validation. The test results show that iBEST accurately estimates the burnup history parameters for the test problems and gives an acceptable level of accuracy for the realistic Mihama-3 problems.

• 시스템엔지니어링학술지
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• 제15권1호
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• pp.51-59
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• 2019

After Fukushima Dai-ichi NPP accident, the need for implementation of diverse and flexible coping strategies (FLEX) became evident. However, to ensure the effectiveness of the safety strategy, it is essential to quantify the uncertainties associated with the station blackout (SBO) scenario as well as the operator actions. In this paper, a systems engineering approach for uncertainty analysis (UA) of a SBO scenario in advanced pressurized water reactor is performed. MARS-KS is used as a best estimate thermal-hydraulic code and is loosely-coupled with Dakota software which is employed to develop the uncertainty quantification framework. Furthermore, the systems engineering approach is adopted to identify the requirements, functions and physical architecture, and to develop the verification and validation plan. For the preliminary analysis, 13 uncertainty parameters are propagated through the model to evaluate the stability and convergence of the framework. The developed framework will ultimately be used to quantify the aleatory and epistemic uncertainties associated with an extended SBO accident scenario and assess the coping capability of APR1400 and the effectiveness of the implemented FLEX strategies.

• 한국멀티미디어학회논문지
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• 제22권3호
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• pp.349-356
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• 2019

When a prescription change occurs in the hospital depending on a patient's improvement status, pharmacists directly classify manually returned pills which are not taken by a patient. There are hundreds of kinds of pills to classify. Because it is manual, mistakes can occur and which can lead to medical accidents. In this study, we have compared YOLO, Faster R-CNN and RetinaNet to classify and detect pills. The data consisted of 10 classes and used 100 images per class. To evaluate the performance of each model, we used cross-validation. As a result, the YOLO Model had sensitivity of 91.05%, FPs/image of 0.0507. The Faster R-CNN's sensitivity was 99.6% and FPs/image was 0.0089. The RetinaNet showed sensitivity of 98.31% and FPs/image of 0.0119. Faster RCNN showed the best performance among these three models tested. Thus, the most appropriate model for classifying pills among the three models is the Faster R-CNN with the most accurate detection and classification results and a low FP/image.

• 시스템엔지니어링학술지
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• 제19권2호
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• pp.18-31
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• 2023

Exploring artificial intelligence and machine learning for nuclear safety has witnessed increased interest in recent years. To contribute to this area of research, a machine learning model capable of accurately predicting nuclear power plant response with minimal computational cost is proposed. To develop a robust machine learning model, the Best Estimate Plus Uncertainty (BEPU) approach was used to generate a database to train three models and select the best of the three. The BEPU analysis was performed by coupling Dakota platform with the best estimate thermal hydraulics code RELAP/SCDAPSIM/MOD 3.4. The Code Scaling Applicability and Uncertainty approach was adopted, along with Wilks' theorem to obtain a statistically representative sample that satisfies the USNRC 95/95 rule with 95% probability and 95% confidence level. The generated database was used to train three models based on Recurrent Neural Networks; specifically, Long Short-Term Memory, Gated Recurrent Unit, and a hybrid model with Long Short-Term Memory coupled to Convolutional Neural Network. In this paper, the System Engineering approach was utilized to identify requirements, stakeholders, and functional and physical architecture to develop this project and ensure success in verification and validation activities necessary to ensure the efficient development of ML meta-models capable of predicting of the nuclear power plant response.

• Earthquakes and Structures
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• 제4권3호
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• pp.241-264
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• 2013

Since the beginning of the twentieth century, the progressive and rapid spread of reinforced concrete (RC) has led to the adoption of mixed masonry-RC solutions, such as the confined masonry. However, together with structures conceived with a definite role for earthquake behaviour, the spreading of RC technology has caused the birth of mixed solutions inspired more by functional aspects than by structural ones, such as: internal masonry walls replaced by RC frames, RC walls inserted to build staircases or raising made from RC frames. Usually, since these interventions rise from a spontaneous build-up, any capacity design or ductility concepts are neglected being designed only to bear vertical loads: thus, the vulnerability assessment of this class becomes crucial. To investigate the non-linear seismic response of these structures, suitable models and effective numerical tools are needed. Among the various modelling approaches proposed in the literature and codes, the authors focus their attention on the equivalent frame model. After a brief description of the adopted model and its numerical validation, the authors aim to point out some specific peculiarities of the seismic response of mixed masonry-RC structures and their repercussions on safety verification procedures (referring in particular way to the non-linear static ones). In particular, the results of non-linear static analyses performed parametrically to various configurations representative of different interventions are discussed.