• Title/Summary/Keyword: safety container

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A Study on Risk Management Plan for Container Terminals - with Safety Accidents - (컨테이너터미널의 리스크 관리 방안 연구 - 안전사고를 중심으로 -)

  • Yeun, Dong-Ha;Choi, Yong-Seok;Kim, Sun-Gu
    • Proceedings of the Korean Institute of Navigation and Port Research Conference
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    • 2015.10a
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    • pp.163-164
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    • 2015
  • This paper analyze a pattern and a cause of safety accident occupied in work filed of container terminals, calculate risk index considering accident frequency and severity, and then provide the relative risk assessment. Based on this, this paper provides the priority of risk reducing method in container terminals, proposes the risk management plan.

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Strength Safety Evaluation of Composite Pressure Container for Hydrogen Fuel Tanks (수소연료탱크용 복합소재 압력용기에 관한 강도안전성 평가연구)

  • Kim, Chung-Kyun;Kim, Do-Hyun
    • Journal of the Korean Institute of Gas
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    • v.15 no.1
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    • pp.30-34
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    • 2011
  • This paper presents a strength safety evaluation of composite pressure container for hydrogen fuel tanks with a storage capacity of 104 liter and 70MPa pressure. The carbon fiber composite container is manufactured by an aluminum liner of Al6061-T6 and composite multi-layers of hoop winding layer in circumferential direction, $12^{\circ}C$ inclined winding layer and $70^{\circ}C$winding layer in helical direction respectively. The FEM results on the strength safety of composite fuel tanks were evaluated with a criterion of design safety of US DOT-CFFC and KS B ISO 11119-2 codes. The FEM computed results indicate that the proposed design model of 104 liter composite container is safe based on two strength safety codes. But, the computed results of carbon fiber fuel tanks based on US DOT-CFFC code is safer compared with that of KS B ISO 11119-2. Thus the hydrogen gas pressure container of 70MPa may be evaluated and designed by US DOT-CFFC code for more strength safety.

Shape Change Analysis of a Small Propane Container by Pressure Test (소형프로판용기 내압시험을 통한 용기의 형상변화 분석)

  • Lee, Jong-Sang;Jang, Kap-Man;Lee, Yoon Hyoung;Yim, Sang-Sik;Lee, Jin-Han
    • Journal of the Korean Institute of Gas
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    • v.18 no.6
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    • pp.40-44
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    • 2014
  • In this study, it is analyzed that a change in the shape of small propane containers made of STS304 when increasing of internal pressure. When internal pressure of a small propane container increased, bottom of end plate is convexly changed. This test is applied to a water bath pressure test to analyze the characteristics of the container. Water bath is able to analyze relationship between internal pressure and volume. In result, shape change section is confirmed because bottom of end plate is convexly changed. In addition, this section tend to decrease internal pressure because a volume increment increase out of proportion to pressure. The results of this study are expected to contribute to improving the safety of the pressure vessel, as well as various small propane container.

Analysis of Logistics Effects in Enterprises by the Medium of Standardization of Packing Containers (포장용기 표준화를 통한 기업 내(內) 물류효과 분석)

  • Won, You-Jon;Kim, Jin-Ho;Kim, Dong-Kyu
    • Journal of the Korea Safety Management & Science
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    • v.14 no.4
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    • pp.193-203
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    • 2012
  • In the limitless competition era of the 21st century, cost reduction is being highlighted as one of survival strategies of businesses. The first item for cost reduction of businesses is logistical costs. The most keenly required thing for this is to remove unnecessary elements, and the best way to realize it to cut down processes using automatic facilities. Packing container in logistics is like a facility. This study is intended to analyze reduction of costs, improvement of business process and reduction of working force through standardization of standardization, and logistics effects through improvement of environmental images in enterprises.

Assessment of a Pre-conceptual Design of a Spent PWR Fuel Disposal Container (가압경수로형 사용후핵연료 처분용기의 예비 개념설계 평가)

  • Choi, Jong-Won;Cho, Dong-Keun;Lee, Yang;Choi, Heui-Joo;Lee, Jong-Youl
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.4 no.1
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    • pp.41-50
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    • 2006
  • In this paper, sets of engineering analyses were conducted to renew the overall dimensions and configurations of a disposal container proposed as a prototype in the previous study. Such efforts and calculation results can provide new design variables such as the inner basket array type and thickness of the outer shell and the lid & bottom of a spent nuclear fuel disposal container. These efforts include radiation shielding and nuclear criticality analyses to check to see whether the dimensions of the container proposed from the mechanical structural analyses can provide a nuclear safety or not. According to the results of the structural analysis of a PWR disposal container by varying the diameter of the container insert, the Maximum Von Mises stress from the 102 cm-container meets the safety factor of 2.0 for both extreme and normal load conditions. This container also satisfies the nuclear criticality and radiation safety limits. This decrease in the diameter results in a weight loss of a container by $\sim20$ tons.

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Pre-conceptual Design of a Spent PWR Fuel Disposal Container (가압경수로형 사용후핵연료 처분용기의 예비 개념설계 평가)

  • CHO Dong-Keun;CHOI Jongwon;Lee Yang;CHOI Heui-Joo;LEE Jong-Youl
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2005.11a
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    • pp.153-162
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    • 2005
  • In this Paper, sets of engineering analyses were conducted to renew the overall dimensions and configurations of a disposal container proposed as a prototype in the previous study. Such efforts and calculation results can provide new design variables such as the inner basket array type and thickness of the outer shell and the lid & bottom of a spent nuclear fuel disposal container. These efforts include radiation shielding and nuclear criticality analyses to check to see whether the dimensions of the container proposed from the mechanical structural analyses can provide a nuclear safety or not. According to the results of the structural analysis of a PWR disposal container by varying the diameter of the container insert, the Maximum Von Mises stress from the 102 cm container meets the safety factor of 2.0 for both extreme and normal load conditions. This container also satisfies the nuclear criticality and radiation safety limits. This decrease in the diameter results in a weight loss of a container by ${\~}$20 tons.

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A Study on Toxicity Evaluation of Combustion Gases Released from the Residental Container Fire - Efficiency Test for the Fire Gas Mask Filters (주거용 컨테이너 화재시 발생되는 연소가스의 독성 평가에 관한 연구 - 화재용 방독면 filter의 성능평가를 중심으로)

  • Lee Jung Yun;Kim Jeong Hun;Kim Youn-Hi;Jung Ki Chang
    • Journal of the Korean Society of Safety
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    • v.19 no.4 s.68
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    • pp.48-54
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    • 2004
  • The recent Ire incident in an elementary school of Chonan city causes the media focus on the fire safety of residential container buildings. In this study, real fire tests were conducted in this kind of buildings. Combustion products including $O_2,\; CO_2,\;CO,\;NOx,\;SOx,\;HCI,\;HCN$ were measured, and blood samples of lab rats were analyzed in terms of Co-Hb, Glucose, AST(GOT), ALT(GPT), in order to investigate the hazard-reduction effects of employing gas mask protected with filter during the fire emergency of residential container buildings. According to the test results, whether or not employing the filter showed a sheer difference in the toxicity of the fire-induced gases, and then the importance of wearing a gas mask was evidently demonstrated.

A Study on the Safety Measure for Mega Container Ships Calling at Busan New Port from the Perspective of Pilotage (도선 관점에서 본 초대형 컨테이너 선박의 부산신항 내 안전대책 연구)

  • Kim, Chong-hwan;Park, Young-soo;Kim, Dae-won
    • Journal of Navigation and Port Research
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    • v.44 no.3
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    • pp.174-180
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    • 2020
  • With the removal of underwater obstacles in the Busan New Port, the water depth of the pier has been secured up to 17m, and the port authority is constantly responding to the trend of container vessels becoming larger. Also, in 2020, 24,000TEU class container ships are entering to the port, and it is planned to secure the depth in the port to 23 m later in line with this trend. Mega container ships must check in advance the factors to be considered depending on the situation at the time, and for this, it is judged that information sharing among stakeholders is necessary. In this paper, to understand the effect of the corresponding route because of the mega container ships, a transit safety evaluation was conducted based on statistical data on ship entry and departure and maneuver characteristics of corresponding ships. The result showed that the transit of the mega container ships has increased up to 8.4% comparing to the risk of 4,000TEU class container ships. Additionally, safety measures such as minimum safety depth and tug operation plans were presented by gathering opinions on operational characteristics from the perspective of pilotage for safe transit in the Busan New Port area. Through this, it is considered that it will be possible to contribute to the prevention of accidents when entering and leaving the Busan New Port.

An Approach to the Localization of Technology for a Transport and Storage Container for Very Low-Level Radioactive Liquid Waste

  • Shin, Seung Hun;Choi, Woo Nyun;Yoon, Seungbin;Lee, Un Jang;Park, Hye Min;Kim, Hee Reyoung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.20 no.1
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    • pp.127-131
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    • 2022
  • The structural safety of prototype transport and storage containers for very low-level radioactive liquid waste was experimentally estimated for its localization development. Transport containers for radioactive liquid waste have been researched and developed, however, there are no standardized commercial containers for very low-level radioactive waste in Korea. In this study, the structural safety of the designated IP-2 type container capable of transporting and temporarily storing large amounts of very low-level liquid waste, which is generated during the operation and decommissioning of nuclear power plants, was demonstrated. The stacking and drop tests, which were conducted to determine the structural integrity of the container, verified that there was no external leakage of the contents in spite of its structural deformation due to the drop impact. This study shows the effort required for the localization of the technology used in manufacturing transport and storage containers for very low-level radioactive liquid waste, and the additional structural reinforcement of the container in which the commercial intermediate bulk container (IBC) external frame was coupled.