• 제목/요약/키워드: technology level assessment

검색결과 1,042건 처리시간 0.031초

천리안 해양위성 2호 Level-1 영상의 품질관리를 위한 지상국 시스템 개선 (Improvement of GOCI-II Ground System for Monitoring of Level-1 Data Quality)

  • 이순주;오금희;강금실;최우창;최종국;안재현
    • 대한원격탐사학회지
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    • 제39권6_2호
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    • pp.1529-1539
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    • 2023
  • 바다의 색을 관측하여 해양환경을 관측하는 천리안 해양위성 2호(Geostationary Ocean Color Imager-II, GOCI-II)의 자료는 지상국 시스템에서 다양한 보정과정을 거쳐 Raw~Level 2 (L2)로 생산되는데, 각 처리 단계에서 발생하는 품질 정확도는 단계별로 누적되어 위성자료의 오차가 점차 증폭된다. 이에 GOCI-II의 Level-1A/B (L1A/B) 자료에서 발생할 수 있는 광학적 품질 및 위치보정 성능 오차를 측정할 수 있도록 GOCI-II 지상국 시스템을 개선하였다. 신규로 구축된 광학적 품질 및 위치보정 성능 평가 모듈(Radiometric and Geometric Performance Assessment Module, RGPAM)은 시험 운영을 통해 성능 측정, 측정 결과의 표출 및 저장 등 기능들이 정상 운영됨을 확인하였다. RGPAM을 통해 측정된 성능들은 향후 GOCI-II 검출기의 감도 저하에 따른 실시간 복사보정 모델 개선, 위성 L1A/B 자료의 품질 일관성 확인 및 이슈사항에 대한 재보정 방안 마련을 위한 기초자료로 활용될 수 있을 것으로 기대한다.

External dose assessment for workers dismantling the bio-shield of a commercial power nuclear reactor: Case study of Kori-1, Korea

  • Lee, ChoongWie;Lee, Donghyun;Kim, Hee Reyoung;Lee, Seung Jun
    • Nuclear Engineering and Technology
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    • 제52권9호
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    • pp.2085-2091
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    • 2020
  • The license for Kori-1, the first commercial reactor in Busan, Korea, was terminated in June 2017; therefore, preparations are being made for its decommissioning. Because the radioactivity of Bio-shield varies greatly throughout the structure, the doses received by the workers depend on the location, order, and duration of dismantling operations. Thus, a model for evaluating the worker external dose during the dismantling of the Kori-1 bio-shield was developed, and work scenarios for dose assessment were designed. The Dose evaluation code VISIPLAN was used for dose assessment. The dose rate around the bio-shield was evaluated and the level of exposure to the operator was evaluated according to the work scenario. The maximum annual external dose was calculated as 746.86 mSv for a diamond wire saw operator under dry cutting conditions, indicating that appropriate protective measures, such as changing dismantling sequence, remote monitoring, shield installation, and adjustment of work team are necessary for the safe dismantling of the bio-shield. Through these protective measures, it was found that the worker's dose could be below the dose limit.

KBS-3 방식 고준위방폐물 심층처분장 FEP 분석을 통한 국내 사용후핵연료 심층처분시설 방사선학적 안전성 평가용 지권영역 주요 프로세스 항목 및 상대적 중요도 도출 (Draft List and Relative Importance of Principal Processes in the Geosphere to be Considered for the Radiological Safety Assessment of the Domestic Geological Disposal Facility through Analyzing FEPs for KBS-3 Type Disposal Repository of High-level Radioactive Waste(HLW))

  • 김석훈;이동현;박동극
    • 방사선산업학회지
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    • 제17권1호
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    • pp.33-44
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    • 2023
  • The deep geological repository of high-level radioactive waste shall be designed to meet the safety objective set in the form of radiation dose or corresponding risk to protect human and the environment from radiation exposure. Engineering feasibility and conformity with the safety objective of the facility conceptual design can be demonstrated by comparing the assessment result using the computational model for scenario(s) describing the radionuclide release and transport from repository to biosphere system. In this study, as the preliminary study for developing the high-level radioactive waste disposal facility in Korea, we reviewed and analyzed the entire list of FEPs and how to handle each FEP from a general point of view, which are selected for the geosphere region in the radiological safety assessment performed for the license application of the KBS-3 type deep geological repository in Finland and Sweden. In Finland, five FEPs (i.e., stress redistribution, creep, stress redistribution, erosion and sedimentation in fractures, methane hydrate formation, and salt exclusion) were excluded or ignored in the radionuclide release and transport assessment. And, in Sweden, six FEPs (i.e., creep, surface weathering and erosion, erosion/sedimentation in fractures, methane hydrate formation, radiation effects (rock and grout), and earth current) were not considered for all time frames and earthquake out of a total of 25 FEPs for the geosphere. Based on these results, an FEP list (draft) for the geosphere was derived, and the relative importance of each item was evaluated for conducting the radiological safety assessment of the domestic deep geological disposal facility. Since most of information on the disposal facility in Korea has not been determined as of now, it is judged that all FEP items presented in Table 3 should be considered for the radiological safety assessment, and the relative importance derived from this study can be used in determining whether to apply each item in the future.

철도차량 운전자교육을 위한 훈련용 시뮬레이터의 설계 (Design of Train Driving Simulator)

  • 이지선;박성호;최종묵
    • 한국철도학회:학술대회논문집
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    • 한국철도학회 2005년도 춘계학술대회 논문집
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    • pp.175-180
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    • 2005
  • As the high performance computer system increases, improving of reality and usefulness causes the virtual environment of simulator to be used widely as training and assessment tool. Although some domestic companies have developed train driving simulators since about mid of 1990s, accumulation of technology and experience is not yet sufficient compared to foreign makers. This paper describes system composition, training and assessment regimes for high level train driving simulator. When the subsystems are designed, comprehension of train system is emphasized and the functions that simulator should provide are discussed.

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Development of MURCC code for the efficient multi-unit level 3 probabilistic safety assessment

  • Jung, Woo Sik;Lee, Hye Rin;Kim, Jae-Ryang;Lee, Gee Man
    • Nuclear Engineering and Technology
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    • 제52권10호
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    • pp.2221-2229
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    • 2020
  • After the Fukushima Daiichi nuclear power plant (NPP) accident, level 3 probabilistic safety assessment (PSA) has emerged as an important task in order to assess the risk level of the multi-unit NPPs in a single nuclear site. Accurate calculation of the radionuclide concentrations and exposure doses to the public is required if a nuclear site has multi-unit NPPs and large number of people live near NPPs. So, there has been a great need to develop a new method or procedure for the fast and accurate offsite consequence calculation for the multi-unit NPP accident analysis. Since the multi-unit level 3 PSA is being currently performed assuming that all the NPPs are located at the same position such as a center of mass (COM) or base NPP position, radionuclide concentrations or exposure doses near NPPs can be drastically distorted depending on the locations, multi-unit NPP alignment, and the wind direction. In order to overcome this disadvantage of the COM method, the idea of a new multiple location (ML) method was proposed and implemented into a new tool MURCC (multi-unit radiological consequence calculator). Furthermore, the MURCC code was further improved for the multi-unit level 3 PSA that has the arbitrary number of multi-unit NPPs. The objectives of this study are to (1) qualitatively and quantitatively compare COM and ML methods, and (2) demonstrate the strength and efficiency of the ML method. The strength of the ML method was demonstrated by the applications to the multi-unit long-term station blackout (LTSBO) accidents at the four-unit Vogtle NPPs. Thus, it is strongly recommended that this ML method be employed for the offsite consequence analysis of the multi-unit NPP accidents.

Status of Environmental Life Cycle Assessment (LCA): Case study of South Korea

  • Odey, Golden;Adelodun, Bashir;Kim, Sang Hyun;Choi, Kyung Sook
    • 한국수자원학회:학술대회논문집
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    • 한국수자원학회 2021년도 학술발표회
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    • pp.455-455
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    • 2021
  • The Life Cycle Assessment (LCA) as an environmental impact assessment tool has received increasing attention over the years. Unlike the water footprint (WF) and carbon footprint (CF) assessments whose focus is only on a single environmental aspect, the LCA systematically analyzes the different impacts along the entire life cycle, making possible the identification of potential environmental tradeoffs. In Korea, LCA has drawn much attention from both industry and academia since the mid-90s. However, the level of Korea-related LCA studies with respect to different sectors in the past 20 years has not been analyzed. This study, therefore, sought to assess the status of environmental Life Cycle Assessment (LCA) studies in Korea, with a view to understanding the current level of sustainability reporting and identify potential research gaps. Online searches of English written articles published between 2000 and 2019 were conducted on Google, Google scholar, Scopus, and Web of Science databases using the Keywords "life cycle assessment", "lca", and "Korea." At the end of the search, about 88 LCA related studies were identified for Korea within the study period. Majority of these studies focused on the construction (49%) and energy (31%) sectors with fewer environmental studies on the transportation (9%), manufacturing (8%), agriculture (2%), and information and communication (1%) industries. Based on publication trend, results show that LCA studies in Korea have been on the rise in the past 20 years, even though the number of publications has not followed a constant pace. In comparison with the economic sectors of the country, reports show an inadequacy in the coverage of major industries of growing economic relevance like the tourism, health, and agriculture, suggesting a need to further increase and improve LCA related studies in these sectors.

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Multi-unit Level 3 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site

  • Kim, Sung-yeop;Jung, Yong Hun;Han, Sang Hoon;Han, Seok-Jung;Lim, Ho-Gon
    • Nuclear Engineering and Technology
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    • 제50권8호
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    • pp.1246-1254
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    • 2018
  • The importance of performing Level 3 probabilistic safety assessments (PSA) along with a general interest in assessing multi-unit risk has been sharply increasing after the Fukushima Daiichi nuclear power plant (NPP) accident. However, relatively few studies on multi-unit Level 3 PSA have been performed to date, reflecting limited scenarios of multi-unit accidents with higher priority. The major difficulty to carry out a multi-unit Level 3 PSA lies in the exponentially increasing number of multi-unit accident combinations, as different source terms can be released from each NPP unit; indeed, building consequence models for the astronomical number of accident scenarios is simply impractical. In this study, a new approach has been developed that employs the look-up table method to cover every multi-unit accident scenario. Consequence results for each scenario can be found on the table, established with a practical amount of effort, and can be matched to the frequency of the scenario. Preliminary application to a six-unit NPP site was carried out, where it was found that the difference between full-coverage and cut-off cases could be considerably high and therefore influence the total risk. Additional studies should be performed to fine tune the details and overcome the limitations of the approach.

환경물질을 제외한 전자부품의 신뢰성 평가 방법 연구 (Reliability Assessment Methods for Electronic Component Removed Environmental Materials)

  • 이종범;조재립
    • 대한안전경영과학회지
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    • 제9권6호
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    • pp.55-68
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    • 2007
  • Recently, all kind of 21C-typed electronic goods show the tendency of hightechnology and digital convergence rapidly. Also, failure mechanism which differs from original goods concept presents. Today, failure mechanism which differs from one that was happened by restricted harmful environment material before adapted the raw of environment material is changing the paradigm of reliability engineering. Thus, when applied the environment matter of original and secondary material at the electronic goods were removed, reliability assessment method and prediction stay into low level. This study suggests as solution to overcome these phenomenon. The study on the management method of environmental restriction substances which is recognized as important element in the reliability assessment about environment material of electronic goods and the study on reliability assessment method of PWB without environment material are progressed.

중소기업을 위한 스마트공장 도입 준비도 진단 체계 개발 및 적용사례연구 (Developing a Framework for Assessing Smart Factory Readiness of SMEs and Case Study)

  • 조지훈;신완선
    • 품질경영학회지
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    • 제47권1호
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    • pp.1-15
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    • 2019
  • Purpose: The purpose of this study is to support SMEs' introduction of smart factories during the $4^{th}$ Industrial Revolution era. Through this study, we developed the readiness assessment framework for SMEs. This study draws practical implications for improving the readiness of SMEs to introduce smart factories. Methods: Readiness Assessment Framework Design method, Case Studies Analysis Results: This study identified SMEs suitable for smart factories and identified key issues for nonconforming companies. And the diagnostic framework has been determined whether it works in a real-life SME environment. Conclusion: In order to succeed in the smart factory deployment, readiness assessment for SMEs should be performed as necessary. Prior to the introduction of smart factories, quality innovation activities should be carried out according to factory level.

Investigation of a management framework for condition assessment of concrete structures based on reusable knowledge and inspection

  • Moodi, Faramarz
    • Computers and Concrete
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    • 제7권3호
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    • pp.249-269
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    • 2010
  • Managing and reusing knowledge in engineering and construction sectors can lead to greater competitive advantage, improved designs, and more effective management of constructed facilities. The use of Information Technology (IT) in design and construction can exploit strategic opportunities for new ways of integration, sharing and facilitating information and knowledge in any field of engineering. The integrating of separate areas of IT can be used to bring a group of experts and specialists in any field of engineering closer together by allowing them to communicate and exchange information and expertise that facilitate knowledge capture, sharing, and reuse. A lack of an advisory management system and a need to marshal all available data in a common format has indicated the need for an integrated engineering computing environment to investigate concrete repair problems. The research described in this paper is based upon an evaluation management system (EMS) which comprising a database management system (REPCON) alongside visualisation technologies and evaluation system (ECON) is developed to produce an innovative platform which will facilitate and encourage the development of knowledge in educational, evolution and evaluation modes of concrete repair. This allows us to create assessment procedures that will allow the current condition of the concrete structure and its components to be expressed numerically using a confidence level (CL) so as to take the best course of action in the repair and maintenance management. The explained rating system, which is related to structural integrity and serviceability of the structure, allows the confidence level to be determined by visual inspection and the descriptive information and pictures taken from an available REPair of CONcrete (REPCON) database.