• Title/Summary/Keyword: elements important for safety

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Shock-Absorbing Safety Mechanism Based on Transmission Angle of a 4-Bar Linkage (4절링크의 전달각에 기초한 충격흡수식 안전기구)

  • Park, Jung-Jun;Kim, Byeong-Sang;Song, Jae-Bok
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.29 no.11 s.242
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    • pp.1534-1541
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    • 2005
  • Unlike industrial manipulators, the manipulators mounted on service robots are interacting with humans in various aspects. Therefore, safety has been one of the most important design issues. Many compliant robot arms have been introduced for safety. It is known that passive compliance method has faster response and higher reliability than active ones. In this paper, a new safety mechanism based on passive compliance is proposed. Passive mechanical elements, specifically transmission angle of the 4-bar linkage, springs and shock absorbing modules are incorporated into this safety mechanism. This mechanism works only when the robot arm exerts contact force much more than the human pain tolerance. Validity of this mechanism is verified by simulations and experiments. It is shown that the manipulator using this mechanism provides higher performance and safety than those using other passive compliance mechanisms or active methods.

A Study on Effective Response to Product Liability for Diamond Tool Industry (다이아몬드공구 산업에 있어서 제조물책임에 대한 효과적인 대응방안에 관한 연구)

  • Lee, Hwa-Ki;Cho, Min-Gyu
    • Journal of the Korea Safety Management & Science
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    • v.14 no.2
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    • pp.71-82
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    • 2012
  • Many countries are enforcing the Product Liability Act to ask the responsibility for the supply of the safe products. Thus, the safety of the product becomes one of the most important elements in modern corporate management. Diamond tool industries producing risk-high products cannot make an except to this situation. This research presents how Diamond tool manufactures in korea to respond effectively to Product Liability through construction of Product Safety Management System.

A Study on the Verification Scheme for Electrical Circuit Analysis of Fire Hazard Analysis in Nuclear Power Plant (원전 화재위험도분석에서 전기회로분석 검증방안에 관한 연구)

  • Yim, Hyuntae;Oh, Seungjun;Kim, Weekyong
    • Journal of the Korean Society of Safety
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    • v.30 no.3
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    • pp.114-122
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    • 2015
  • In a fire hazard analysis (FHA) for nuclear power plant, various electrical circuit analyses are performed in the parts of fire loading analysis, fire modeling analysis, separation criteria analysis, associated circuit analysis, and multiple spurious operation analysis. Thus, electrical circuit analyses are very important areas so that reliability of the analysis results should be assured. This study is to establish essential electrical elements for each analysis for verification of the reliability of the electrical circuit analyses in the fire hazard analysis for nuclear power plants. Applying the results derived by the study to domestic nuclear power plants, it is expected to determine the adequacy of the fire hazard analysis report and contribute to the reliability of the fire hazard analysis of those plants.

SENSITIVITY ANALYSES OF THE USE OF DIFFERENT NEUTRON ABSORBERS ON THE MAIN SAFETY CORE PARAMETERS IN MTR TYPE RESEARCH REACTOR

  • Kamyab, Raheleh
    • Nuclear Engineering and Technology
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    • v.46 no.4
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    • pp.513-520
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    • 2014
  • In this paper, three types of operational and industrial absorbers used at research reactors, including Ag-In-Cd alloy, $B_4C$, and Hf are selected for sensitivity analyses. Their integral effects on the main neutronic core parameters important to safety issues are investigated. These parameters are core excess reactivity, shutdown margin, total reactivity worth of control rods, thermal neutron flux, power density distribution, and Power Peaking Factor (PPF). The IAEA 10 MW benchmark core is selected as the case study to verify calculations. A two-dimensional, three-group diffusion model is selected for core calculations. The well-known WIMS-D4 and CITATION reactor codes are used to carry out these calculations. It is found that the largest shutdown margin is gained using the $B_4C$; also the lowest PPF is gained using the Ag-In-Cd alloy. The maximum point power densities belong to the inside fuel regions surrounding the central flux trap (irradiation position), surrounded by control fuel elements, and the peripheral fuel elements beside the graphite reflectors. The greatest and least fluctuation of the point power densities are gained by using $B_4C$ and Ag-In-Cd alloy, respectively.

A study on the actual condition of counterplan for product liability in small and medium enterprises (중소기업의 제조물 책임(PL) 대응실태에 관한 연구)

  • Park, Roh-Gook;Lee, Song-Ho
    • Proceedings of the Safety Management and Science Conference
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    • 2010.11a
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    • pp.507-516
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    • 2010
  • Product liability as a process has developed significantly in the United Kingdom and the United States of America. The safety of the product becomes one of the most important elements in modern corporate management. The rapid introduction of product liability has recently been a prevalent phenomenon, as global changes arising from rapid development in science and the economy have resulted in a highly interconnected world economy. This thesis was established, based on current literature and business consulting cases in the position of companies, and is one of the operating subjects in a system for legal responsibility in manufactured products.

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Comparison Analysis between the IWRAP and the ES Model in Ulsan Waterway

  • Kim, Dae-Won;Park, Jin-Soo;Park, Young-Soo
    • Journal of Navigation and Port Research
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    • v.35 no.4
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    • pp.281-287
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    • 2011
  • According to the Marine Traffic Safety Law, revised in 2009, Marine Traffic Safety Audit is introduced to secure the safe navigation, to prevent the marine accident and to maximize the efficiency of the port. In this audit system, marine traffic safety assessment is the most important scheme because the primary purpose of the audit system is to identify potential risk elements affecting safe navigation. Even though the reliability of audit result depends on the selection of assessment models, there are no independent assessment models for Korean coastal waters and most of models used in Korea currently are developed by foreign countries. Therefore, the development of the independent assessment model for Korean coastal water is required. This study, prior to the development of independent assessment model, aims to provide a basic data by comparing two foreign assessment models in Ulsan port area with marine accident statistics data.

The Task and Role of the Quality Improvement Facilitator (QI전담자의 주요 업무 및 역할 규명)

  • Kim, Moon-sook;Kim, Hyun-ah;Kim, Yoon-sook
    • Quality Improvement in Health Care
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    • v.21 no.2
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    • pp.40-56
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    • 2015
  • Objectives: To outline overall duties of quality improvement (QI) performers within a health care organization, thus describing their key tasks, including task element-related frequency, importance and difficulty in enough detail. Methods: A DACUM (Developing A CurriculUM) workshop took place to outline overall job activities of QI performers. To examine the scope of their duty and task, we performed a questionnaire survey of 338 QI performers from 111 hospitals. Results: The results of our survey showed that for the task assigned to each QI performer, there were 10 duties, 31 tasks and 119 task elements. Respondents cited a project planning as the most frequent/important duty, and a research was the highest level of difficulty in their duty. They also said that the most frequent task was index management, the most important task was a business plan, and the highest level of difficulty was a practical application of QI research. QI performers added that the most frequent task element was receipt of patient safety reporting in patient safety system, the most important task element was an analysis for patient safety and its improvement, and the highest level of difficulty was a regional influence analysis related to the patient safety and its improvement. Conclusion: To ensure that QI performers play a pivotal role as a manager to better improve patient safety and the quality of health care services, proper training program for them should be developed by reflecting the results of our study.

Nuri-curriculum Daycare Programs Analysis for 3 to 5-year-olds Based on Child Welfare Act Safety Education-Based Content (3-5세 누리과정에 기초한 어린이집 프로그램의 안전교육 내용 분석: 아동복지법을 기준으로)

  • Nam, Hyunjoo;Lee, Sangehee
    • Korean Journal of Childcare and Education
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    • v.15 no.3
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    • pp.39-60
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    • 2019
  • Objective: The purpose of this study was to analyze the Nuri-curriculum daycare programs for 3, 4, and 5-year-olds based on the Child Welfare Act. Methods: Data were analyzed according to the analysis criteria for 195 children's safety education programs in the Nuri-Program. The analyzed data used frequency and percentages. Results: First, life safety education was the most important element. And after looking at the contents category of the Child Welfare Act, the results in order are as follows: "raffic safety"; "Health and hygiene management, including the prevention of contagious diseases and drug abuse"; "Safety measures against disasters"; "Precaution and prevention of disappearance and abduction"; and "Prevention of sexual violence and child abuse." Second, there were many safety education activities in accordance to chronological age (3-to 5-years old). Health and safety by subject, season, and life tools were more frequent. By type of activity, conversation and language activity, fairy tales, and plays were the most common activities. Conclusion/Implications: This suggests the need to systematically plan safety education content through a program that links safety-related laws and elements related to the Nuri curriculum in child care centers.

Regulatory Oversight of Nuclear Safety Culture and the Validation Study on the Oversight Model Components

  • Choi, Young Sung;Jung, Su Jin;Chung, Yun Hyung
    • Journal of the Ergonomics Society of Korea
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    • v.35 no.4
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    • pp.263-275
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    • 2016
  • Objective: This paper introduces the regulatory oversight approaches and issues to consider in the course of safety culture oversight model development in the nuclear field. Common understanding on regulatory oversight and present practices of international communities are briefly reviewed. The nuclear safety culture oversight model of Korea is explained focusing on the development of safety culture definition and components, and their basic meanings. Oversight components are identified to represent the multiple human and organizational elements which can affect and reinforce elements of defense in depth system for nuclear safety. Result of validation study on safety culture components is briefly introduced too. Finally, the results of the application of the model are presented to show its effectiveness and feasibility. Background: The oversight of nuclear licensee's safety culture has been an important regulatory issue in the international community of nuclear safety regulation. Concurrent with the significant events that started to occur in the early 2000s and that had implications about safety culture of the operating organizations, it has been natural for regulators to pay attention to appropriate methods and even philosophy for intervening the licensee's safety culture. Although safety culture has been emphasized for last 30 years as a prerequisite to ensure high level of nuclear safety, it has not been of regulatory scope and has a unique dilemma between external oversight and the voluntary nature of culture. Safety culture oversight is a new regulatory challenge that needs to be approached taking into consideration of the uncontrollable aspects of cultural changes and the impacts on licensee's safety culture. Although researchers and industrial practitioners still struggle with measuring, evaluating, managing and changing safety culture, it was recognized that efforts to observe and influence licensees' safety culture should not be delayed. Method: Safety culture components which regulatory oversight will have to focus on are developed by benchmarking the concept of physical barriers and introducing the defense in depth philosophy into organizational system. Therefore, this paper begins with review of international regulatory oversight approaches and issues associated with the regulatory oversight of safety culture, followed by the development of oversight model. The validity of the model was verified by statistical analysis with the survey result obtained from survey administration to NPP employees in Korea. The developed safety culture oversight model and components were used in the "safety culture inspection" activities of the Korean regulatory body. Results: The developed safety culture model was confirmed to be valid in terms of content, construct and criterion validity. And the actual applicability in the nuclear operating organization was verified after series of pilot "safety culture inspection" activities. Conclusion: The application of the nuclear safety culture oversight model to operating organization of NPPs showed promising results for regulatory tools required for the organizations to improve their safety culture. Application: The developed oversight model and components might be used in the inspection activities and regulatory oversight of NPP operating organization's safety culture.

A Study on the Safety Enhancement of Chemical Plants Using Risk Based Inspection Method (Risk Based Inspection 기법을 이용한 화학공장의 안전성 향상에 관한 연구)

  • 노용해;유진환;서재민;임차순;고재욱
    • Journal of the Korean Society of Safety
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    • v.17 no.3
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    • pp.73-80
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    • 2002
  • The RBI technique proposed by API is composed of three steps. The qualitative RBI method can be used for the purpose of screening the components with high risk. And the quantitative RBI method employs complex risk evaluation model for predicting component risk in a quantitative manner. The inspection program can be optimized based on the results obtained by these RBI technique. The forementioned RBI technique has been applied to a common hydrodesulfurizer unit and the technique is critically evaluated for studying its benefits and limitations, which is the main issue of this thesis. It's conducted that the RBI method can provide a method for defining and measuring the component risk, and also provide a powerful tool for managing many of the important elements of a process plant.