• 제목/요약/키워드: Equipment-specific safety

검색결과 169건 처리시간 0.028초

의료종사자의 안전한 개인보호장비 탈의를 위한 공간 설계에 관한 연구 (Using Design to Make Doffing of Personal Protective Equipment Safer for Healthcare Workers)

  • 마틱 조라나;오예인;임리사
    • 의료ㆍ복지 건축 : 한국의료복지건축학회 논문집
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    • 제26권3호
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    • pp.17-26
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    • 2020
  • Purpose: This paper presents research evidence that the environmental design of the doffing area in a biocontainment unit (BCU) can have a measurable impact on increasing the safety of frontline healthcare workers (HCW) during doffing of high-level personal protective equipment (PPE), and proposes optimized biocontainment unit design. Methods: From 2016 to 2019, The SimTigrate Design Lab conducted 3 consecutive studies, focusing on ways in which the built environment may support or hinder safe doffing. In the first study, to identify the risky behaviors, we observed 56 simulation exercises with HCWs in 4 BCUs and 1 high-fidelity BCU mockup. In the second study, we tested the effectiveness of a redesigned doffing area on improving the HCWs performance and used simulation, observation, and rapid prototyping in 1 high-fidelity mockup of a doffing area. In a follow-up study, we used simulation and co-design with HCWs to optimize the design of a safer doffing area in a full-size pediatric BCU mock-up. Results: We identified 11 specific risky behaviors potentially leading to occupational injury, or contamination of the PPE, or of the environment. We developed design strategies to create a space for safer doffing. In the second study, in a redesigned doffing area, the overall performance of HCW improved, and we observed a significant decrease in the number of risky behaviors; some risky behaviors were eliminated. There was a significant decrease in physical and cognitive load for the HCWs. Finally, we propose an optimized layout of a BCU for a safer process of PPE doffing. Implications: The proposed BCU design supports better staff communication, efficiency, and automates safer behaviors. Our findings can be used to develop design guidelines for spaces where patients with other highly infectious diseases are treated when the safety of the patient-facing HCWs is of critical importance.

원자력발전소 전기기기의 보수, 교체 방법론 (Repair and Replacement Methodology for Electrical Equipment Used in Nuclear Power Plants)

  • 박철희;박완규;이만복;김춘삼
    • 전력전자학회:학술대회논문집
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    • 전력전자학회 2018년도 전력전자학술대회
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    • pp.177-179
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    • 2018
  • After Fukushima nuclear accident at 2011, nuclear industrial has been focused on operation and maintenance phase, not design and construction phase. Continued good operating performance of nuclear power plants has been the best critical issue to nuclear utilities. Replacement for complete components as well as parts of components is being procured because nuclear utilities must maintain safety and reliability of operating nuclear power plants. However, many suppliers and manufacturers are giving up a nuclear quality assurance program under reduction in new construction of nuclear power plants. It is able to be increased difficulty in procuring spare parts to support operations and maintenance of nuclear power plants. Over 20% of nuclear power plant equipment in some countries is obsolete. Owing to obsolescence of nuclear safety-related items and/or withdrawing a nuclear quality assurance program of suppliers and manufactures, some replacement item and part might be procured to the item not covered by appendix B to USNRC 10 CFR Part 50. Under various methods of the nuclear repair and replacement methodology, utilities are supposed to establish a typical program for a repair and replacement of an electrical equipment and its parts in conjunction with a nuclear quality assurance. Concerning this typical program, this study suggests the repair and replacement methodology of electrical equipments used in nuclear power plants by procurement of a power supply, based on nuclear regulations, codes, standards, guidelines, specific and general technical information, etc..

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밀폐공간 질식재해 자료 분석을 통한 질식재해 요인 분석 (2005-2015) (Analysis of Suffocating Accidents in Confined Spaces in the Past 10 Years (2005-2015))

  • 이정완;김태형;하현철;박승욱;안광석
    • 한국산업보건학회지
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    • 제26권4호
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    • pp.436-444
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    • 2016
  • Objectives: Despite recent efforts to prevent suffocation disasters, a number of confined space accidents still happen and each year deaths continue to occur. There have been insufficient studies on the dangers of various potential disaster sites, such as manholes, septic tanks, reactors, and other tanks according to type, characteristics, task-specific disasters, equipment specific disasters, etc. The purpose of this study was to analyze recent suffocation disasters based on place and properties. Methods: In this study, we analyzed confined space accident cases from 2005 to 2015 in Korea and grouped them by type, size, monthly occurrence, continuous service period, accident location, person-specific group, age, employment, structural work and subcontracting work. We studied examples of accidents developed in other countries. Results: (1) We reviewed confined-space accident statistics, compared legal standards and analyzed cases of suffocation accidents in the United States and Japan. (2) Using a case study report from the Korea Occupational Safety & Health Agency, we specified confined-space accident statistics based on place, person-specific group, age, employment, structural work and subcontracting work. As a result we generated some precautions about confined-space accidents for the prevention of such accidents. Conclusions: Conclusions: Statistical analysis of recent suffocation disaster cases was performed to establish improvement measures, compare practices from developed countries, and develop precautionary measures accordingly. In this study, we presented the causes of disaster that occur in a confined space and proposed related preventive measures.

이동식 부탄 연소기의 안전기준 개정을 위한 기초 연구 (Fundamental Study for Reformation of Safety Standard about Portable Butane Gas Range)

  • 김수익;금국빈;유병훈;이창언;김영구
    • 한국연소학회지
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    • 제19권4호
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    • pp.35-41
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    • 2014
  • The experiment was conducted to measure temperature and pressure around operating portable butane gas ranges with oversized cookwares. In this experiment, portable butane gas range with different safety equipment and two kinds of oversized cookware, each of which is made of aluminum alloy and rock, was used. As a result, temperature of the bottom of the butane and the pressure of butane barrel tend to aligned with each other. Through this result, it is reasonable that a safety criteria can be decided based on the temperature of the bottom of butane. Especially, portable butane gas ranges are safely conducted under the condition of the temperature is under 50 degree and pressure is under 500 kPa, respectively, at the bottom of the butane barrel.

A Multiplex PCR Method for the Detection of Genetically Modified Alfalfa (Medicago sativa L.) and Analysis of Feral Alfalfa in South Korea

  • Choi, Wonkyun;Kim, Il Ryong;Lim, Hye Song;Lee, Jung Ro
    • Proceedings of the National Institute of Ecology of the Republic of Korea
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    • 제1권1호
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    • pp.83-89
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    • 2020
  • Methods for detecting the presence of genetically modified (GM) crops are evolving to comply with legislation and to enhance monitoring by biotechnology companies and regulators. In order to cover a broad range of detection methods for a new GM crop, conventional multiplex PCR methods are required. Based on the genetic information on three GM alfalfa varieties (J101, J163, and KK179), which were recently approved in South Korea, we developed a fast, reliable, and highly specific multiplex polymerase chain reaction (PCR) method with basic PCR equipment and inexpensive reagents. To validate and verify the newly developed multiplex PCR method, we applied a limit of detection assay and random reference material analysis. We also monitored the unintentional environmental release of GM alfalfa in South Korea by performing the multiplex PCR analysis with 91 feral alfalfa specimens collected from 2000 to 2018. Our methodology is a sensitive, simple, quick, and inexpensive tool for detecting and identifying three GM alfalfa varieties.

Musculoskeletal Model for Assessing Firefighters' Internal Forces and Occupational Musculoskeletal Disorders During Self-Contained Breathing Apparatus Carriage

  • Wang, Shitan;Wang, Yunyi
    • Safety and Health at Work
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    • 제13권3호
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    • pp.315-325
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    • 2022
  • Background: Firefighters are required to carry self-contained breathing apparatus (SCBA), which increases the risk of musculoskeletal disorders. This study assessed the newly recruited firefighters' internal forces and potential musculoskeletal disorders when carrying SCBA. The effects of SCBA strap lengths were also evaluated. Methods: Kinematic parameters of twelve male subjects running in a control condition with no SCBA equipped and three varying-strapped SCBAs were measured using 3D inertial motion capture. Subsequently, motion data and predicted ground reaction force were inputted for subject-specific musculoskeletal modeling to estimate joint and muscle forces. Results: The knee was exposed to the highest internal force when carrying SCBA, followed by the rectus femoris and hip, while the shoulder had the lowest force compared to the no-SCBA condition. Our model also revealed that adjusting SCBA straps length was an efficient strategy to influence the force that occurred at the lumbar spine, hip, and knee regions. Grey relation analysis indicated that the deviation of the center of mass, step length, and knee flexion-extension angle could be used as the predictor of musculoskeletal disorders. Conclusion: The finding suggested that the training of the newly recruits focuses on the coordinated movement of muscle and joints in the lower limb. The strap lengths around 98-105 cm were also recommended. The findings are expected to provide injury interventions to enhance the occupational health and safety of the newly recruited firefighters.

화학물질관리법상의 유해화학물질 안전관리 개선방안 연구 : 안전성평가 사례 중심 (Development on the Safety Management System of Hazardous Chemicals under the Chemicals Control Act: Focusing on Safety Assessment System)

  • 유병태;이은별;김종구
    • 한국안전학회지
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    • 제34권3호
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    • pp.96-101
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    • 2019
  • Chemicals Control Act have been strengthened to control more safely hazardous chemicals from 2015. In particular, the standards for the installation and management of handling facilities was enhanced with specific regulations depending on type of the facilities and the hazardous chemicals. However, some standards for handling facilities caused difficulties in implementing the strengthened standards due to various field conditions, such as lack of physical space. The Ministry of Environment is implementing Safety Assessment System (SAS) to solve these problems since 2018. However, many plants have difficulties in preparing alternative methods to pass the safety evaluation. The purpose of this study was to review and analyze the SAS and to suggest alternative measures in terms of management and technical aspects through the case study of hydrochloric acid storage tanks. The following safety solutions were suggested for handling facilities that had insufficient the space and capacity for the retaining wall due to physical space. Firstly, insufficient space was resolved by introducing equipment relocation or demolition, and retaining wall expansion. Secondly, the wall of the surrounding buildings was used as an alternative to the retaining wall with additional chemical resistant treatment. Finally, sensor installation and facility inspection were suggested as ways to improve chemical safety. Therefore, improvement of chemical accident prevention system is required not only in terms of facilities supplementation but also management aspect. The results of this study are expected to be available for similar facilities and will be based on the preparation of additional safety assessment as alternatives measures in the future.

GFRP-폼 샌드위치 복합재료로 설계된 구체 비행 시뮬레이터의 구조 안정성 평가 (Structural Safety Analysis of a Spherical Flight Simulator Designed with a GFRP-Foam Sandwich Composite)

  • 홍채영;지우석
    • Composites Research
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    • 제32권5호
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    • pp.279-283
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    • 2019
  • 구체 비행 시뮬레이터는 6자유도 운동과 무제한 회전 운동을 정밀하고 신속하게 제어하는 비행 훈련용 시뮬레이터이다. 이러한 시뮬레이터를 제작하기 위해서는 고강도 경량화 설계 및 검증이 필요하다. 본 연구에서는 유리섬유강화플라스틱과 폼코어로 구성된 샌드위치 복합재를 이용하여 높은 비강도와 비강성을 확보하고, 내부에 T형 스테인리스 스틸 프레임을 삽입하여 하중에 의한 구체 곡률 변형이 최소화되도록 시뮬레이터를 설계하였다. 그 결과 구체가 접촉하는 각 영역에 균일한 토크 전달이 가능해지고 제어 정확도를 높일 수 있다. 시뮬레이터의 구조 안정성 평가를 위해 유한요소해석을 수행하였으며 재료에 대한 기계적 물성은 ASTM 규격에 따라 측정되었다. 하중 조건은 중력가속도를 고려하고 실제 탑재될 장비와 사용자의 무게를 200 kg으로 가정하였다. 두 가지 상황을 모사하여 하중과 자중에 의해 시뮬레이터에 작용하는 응력과 변위를 해석하고 안전성을 검증하였다.

구조물 및 기기의 한계성능 평가를 위한 고진동수 지진 특성을 반영한 응답스펙트럼 형상 (A Shape of the Response Spectrum for Evaluation of the Ultimate Seismic Capacity of Structures and Equipment including High-frequency Earthquake Characteristics)

  • 임승현;최인길
    • 한국지진공학회논문집
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    • 제24권1호
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    • pp.1-8
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    • 2020
  • In 2016, an earthquake occurred at Gyeongju, Korea. At the Wolsong site, the observed peak ground acceleration was lower than the operating basis earthquake (OBE) level of Wolsong nuclear power plant. However, the measured spectral acceleration value exceeded the spectral acceleration of the operating-basis earthquake (OBE) level in some sections of the response spectrum, resulting in a manual shutdown of the nuclear power plant. Analysis of the response spectra shape of the Gyeongju earthquake motion showed that the high-frequency components are stronger than the response spectra shape used in nuclear power plant design. Therefore, the seismic performance evaluation of structures and equipment of nuclear power plants should be made to reflect the characteristics of site-specific earthquakes. In general, the floor response spectrum shape at the installation site or the generalized response spectrum shape is used for the seismic performance evaluation of structures and equipment. In this study, a generalized response spectrum shape is proposed for seismic performance evaluation of structures and equipment for nuclear power plants. The proposed response spectrum shape reflects the characteristics of earthquake motion in Korea through earthquake hazard analysis, and it can be applied to structures and equipment at various locations.

Valve core shapes analysis on flux through control valves in nuclear power plants

  • Qian, Jin-yuan;Hou, Cong-wei;Mu, Juan;Gao, Zhi-xin;Jin, Zhi-jiang
    • Nuclear Engineering and Technology
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    • 제52권10호
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    • pp.2173-2182
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    • 2020
  • Control valves are widely used to regulate fluid flux in nuclear power plants, and there are more than 1500 control valves in the primary circuit of one nuclear power plant. With their help, the flux can be regulated to a specific level of water or steam to guarantee the energy efficiency and safety of the nuclear power plant. The flux characteristics of the control valve mainly depend on the valve core shape. In order to analyze the effects of valve core shapes on flux characteristics of control valves, this paper focuses on the valve core shapes. To begin with, numerical models of different valve core shapes are established, and results are compared with the ideal flux characteristics curve for the purpose of validation. Meanwhile, the flow fields corresponding to different valve core shapes are investigated. Moreover, relationships between the valve core opening and the outlet flux under different valve core shapes are carried out. The flux characteristics curve and equation are proposed to predict the outlet flux under different valve core openings. This work can benefit the further research of the flux control and the optimization of the valve core for control valves in nuclear power plants.