• 한국재난정보학회 논문집
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• 제12권4호
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• pp.403-411
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• 2016

본 연구의 목적은 건설안전문화수준에 대한 정량적 평가를 위한 평가지표를 개발하여 건설현장의 안전문화수준 및 각 안전문화 요소의 수준을 평가함으로써 사고 예방을 위해 중점적으로 개선하여야 하는 분야를 제시할 수 있도록 하기 위한 것이다. 이 논문에서는 안전문화에 대한 선행연구를 분석하여 기존 안전문화 연구에서 안전문화의 중요 요소로 도출된 항목들을 계층적으로 분류하고 분류된 안전문화 요소에 대해 건설현장 전문가들의 의견을 반영한 AHP 분석방법론을 이용하여 건설안전문화 평가지표를 제시하였다. 건설안전문화 평가지표는 리더십, 시스템, 개인적 특성의 세부 항목들을 구조화하고 쌍대비교하여 가중치를 도출함으로써 세부 중요 평가지표를 정량화하여 건설안전문화 수준을 평가할 수 있도록 하였다. 본 연구를 통해 개발한 건설 안전문화 평가지표를 활용하여 건설현장 안전문화 평가를 실시함으로써 각 건설현장 안전문화 정착을 위해 개선하여야 하는 방향을 도출하고 건설현장 안전사고 예방에 기여하고자 한다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.499-500
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• 2004

• Journal of Radiation Protection and Research
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• 제29권1호
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• pp.41-48
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• 2004

A safety assessment code, called SAGE (Safety Assessment Groundwater Evaluation), has been developed to describe post-closure radionuclide releases and potential radiological doses for low- and intermediate-level radioactive waste (LILW) disposal in an engineered vault facility in Korea. The conceptual model implemented in the code is focused on the release of radionuclide from a gradually degrading engineered barrier system to an underlying unsaturated zone, thence to a saturated groundwater zone. The radionuclide transport equations are solved by spatially discretizing the disposal system into a series of compartments. Mass transfer between compartments is by diffusion/dispersion and advection. In all compartments, radionuclides ate decayed either as a single-member chain or as multi-member chains. The biosphere is represented as a set of steady-state, radionuclide-specific pathway dose conversion factors that are multiplied by the appropriate release rate from the far field for each pathway. The code has the capability to treat input parameters either deterministically or probabilistically. Parameter input is achieved through a user-friendly Graphical User Interface. An application is presented, which is compared against safety assessment results from the other computer codes, to benchmark the reliability of system-level conceptual modeling of the code.

• 한국항행학회논문지
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• 제20권4호
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• pp.285-291
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• 2016

CNS/ATM 분야에서 안전 평가는 시스템을 개발하는데 반드시 필요한 개발 활동이다. 현재까지, 안전 평가와 관련된 많은 참고할 만한 자료들이 있으나 CNS/ATM분야에서 무엇을 어떻게 적용해야 할지 명확하게 명시된 자료는 없다. 또 다른 문제는 DO-278A기반으로 소프트웨어를 개발하기 위해서는 개발하고자 하는 소프트웨어에 대한 소프트웨어 보증 수준이 결정되어 있어야 한다. 하지만 개발 보증 수준을 결정하는 체계도 또한 정의되어 있지 않다. 이와 같은 문제를 해결하기 위해 본 논문에서는 ICAO Doc 9689에 정의된 안전 목표 수준을 기반으로 한 위험 평가를 수행하기 위한 방법을 제시한다. 항행 안전 시스템에서 일반적으로 적용 가능하도록 하기 위해 위험 평가 수행 절차를 수학적으로 표현하였으며 위험 평가를 위해 필요한 위험원의 심각도 분류, 발생 확률, 시스템 안전 목표 수준 등을 정의하고 위험 평가를 수행하기 위해 이벤트 트리 분석 절차를 적용하는 방법을 설명하였다.

• Nuclear Engineering and Technology
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• 제50권8호
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• pp.1234-1245
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• 2018

The risk of multi-unit nuclear power plants (NPPs) at a site has received considerable critical attention recently. However, current probabilistic safety assessment (PSA) procedures and computer code do not support multi-unit PSA because the traditional PSA structure is mostly used for the quantification of single-unit NPP risk. In this study, the main purpose is to develop a multi-unit Level 2 PSA method and apply it to full-power operating six-unit OPR1000. Multi-unit Level 2 PSA method consists of three steps: (1) development of single-unit Level 2 PSA; (2) extracting the mapping data from plant damage state to source term category; and (3) combining multi-unit Level 1 PSA results and mapping fractions. By applying developed multi-unit Level 2 PSA method into six-unit OPR1000, site containment failure probabilities in case of loss of ultimate heat sink, loss of off-site power, tsunami, and seismic event were quantified.

• 한국항행학회논문지
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• 제19권1호
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• pp.41-47
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• 2015

최근 국내에서 A-SMGCS (advance surface movement ground control systems) 레벨 IV단계를 구현하기 위한 연구가 활발히 진행 중에 있다. 전체 A-SMGCS 시스템의 안전을 확보하기 위하여 안전성 평가가 필요하며, 유로컨트롤에서는 A-SMGCS의 안전성 평가를 위하여 기능별 위험요소 평가, 예비시스템 안전성 평가, 그리고 시스템 안전성 평가를 수행하도록 권고하고 있다. 본 논문에서는 기능별 위험요소 평가 방법을 통하여 전체 A-SGMCS의 위험요소를 식별한다. 따라서 A-SMGCS레벨 IV시스템에 대하여 29가지 위험 요소를 식별하고 각 위험요소의 심각도를 평가하는 자료로 활용할 것이다.

• 한국의료질향상학회지
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• 제22권2호
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• pp.43-73
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• 2016

Purpose: The aims of this study were to assess the presence of core patient safety practices in Korean hospitals and assess the differences in reporting and learning systems of patient safety, infrastructure, and safe practices by hospital characteristics. Methods: The authors developed a questionnaire including 39 items of patient safety staffing, health information system, reporting system, and event-specific prevention practices. The survey was conducted online or e-mail with 407 tertiary, general and specialty hospitals. Results: About 90% of hospitals answered the self-reporting system of patient safety related events is established. More than 90% of hospitals applied incidence monitoring or root cause analysis on healthcare-associated infection, in-facility pressure ulcers and falls, but only 60% did on surgery/procedure related events. More than 50% of the hospitals did not adopted present on admission (POA) indicators. One hundred (80.0%) hospitals had a department of patient safety and/or quality and only 52.8% of hospitals had a patient safety officer (PSO). While 82.4% of hospitals used electronic medical records (EMRs), only 53% of these hospitals adopted clinical decision support function. Infrastructure for patient safety except EMRs was well established in training, high-level and large hospitals. Most hospitals implemented prevention practices of adverse drug events, in-facility pressure ulcers and falls (94.4-100.0%). But prevention practices of surgery/procedure related events had relatively low adoption rate (59.2-92.8%). Majority of prevention practices for patient safety events were also implemented with a relatively modest increase in resources allocated. Conclusion: The hospital-based reporting and learning system, EMRs, and core evidence-based prevention practices were implemented well in high-level and large hospitals. But POA indicator and PSO were not adopted in more than half of surveyed hospitals and implementation of prevention practices for specific event had low. To support and monitor progress in hospital's patient safety effort, national-level safety practices set is needed.

• 한국유기농업학회지
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• 제14권2호
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• pp.139-157
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• 2006

Biotechnology has reached the level of giving birth to new forms of life and with this is a growing controversy in the conflict between science and ethics. Especially, GMOs are closely linked to the food products we consume and thus, the majority of the public shows a very sensitive reaction to the safety of GMO food products. Many perspectives arose surrounding the issues of safety on the human body and the ecology. This outlines diverse structural mechanisms to be set up to ensure safety such as risk assessment, risk management etc. Despite the precautionary principle guaranteed in many ways, the problem arises whether and how this principle can be taken in the safety assessment. GMOs due to its uniqueness do not end with just the possession of the technology involved but must also be considered with the prerequisite that they could be cultured again. Therefore the reinforcement of safety assessment system is necessary. That is, the reinforcement of risk assessment including field tests, the consideration of socio-economic effects, the coordinated system of relevant authorities, the development of technology for safety assessment.

• Safety and Health at Work
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• 제9권1호
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• pp.30-41
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• 2018

Background: The purpose of the work is to develop a system that allows processing of information for analysis and industrial risk management, to monitor the level of industrial safety and to perform necessary measures aimed at the prevention of accidents, casualties, and development of professional diseases for effective management of industrial safety at hazardous industrial sites. Methods: Risk assessment of accidents and incidents is based on expert evaluations. Based on the lists of criteria parameters and their possible values, provided by the experts, a unified information and analytical database is compiled, which is included in the final interrogation questionnaires. Risk assessment of industrial injuries and occupational diseases is based on statistical methods. Results: The result of the research is the creation of Guidelines for risk management on hazardous industrial sites of the Republic of Kazakhstan. The Guidelines determine the directions and methods of complex assessment of the state of industrial safety and labor protection and they could be applied as methodological basis at the development of preventive measures for emergencies, casualties, and incidents at hazardous industrial sites. Conclusion: Implementation of the information-analytical system of risk level assessment allows to analyze the state of risk of a possible accident at industrial sites, make valid management decisions aimed at the prevention of emergencies, and monitor the effectiveness of accident prevention measures.

• Nuclear Engineering and Technology
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• 제50권8호
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• pp.1217-1233
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• 2018

Following a surge of interest in multi-unit risk in the last few years, many recent studies have suggested methods for multi-unit probabilistic safety assessment (MUPSA) and addressed several related aspects. Most of the existing studies though focused on two-unit nuclear power plant (NPP) sites or used rather simplified probabilistic safety assessment (PSA) models to demonstrate the proposed approaches. When considering an NPP site with three or more units, some approaches are inapplicable or yield very conservative results. Since the number of such sites is increasing, there is a strong need to develop and validate practical approaches to the related MUPSA. This article provides several detailed approaches that are applicable to multi-unit Level 1 PSA for sites with up to six or more reactor units. To validate the approaches, a multi-unit Level 1 PSA model is developed and the site core damage frequency is estimated for each of four representative multi-unit initiators, as well as for the case of a simultaneous occurrence of independent single-unit initiators in multiple units. For this purpose, an NPP site with six identical OPR-1000 units is considered, with full-scale Level 1 PSA models for a specific OPR-1000 plant used as the base single-unit models.