• Title/Summary/Keyword: storage safety

Search Result 1,765, Processing Time 0.026 seconds

An Estimation of the Consequence Analysis for an Underground Installation of the LPG Storage Tanks (소형 LPG 저장탱크 매몰 설치에 대한 피해영향평가)

  • Song, Dong-Woo;Jun, Woon-Young;Lee, Su-Kyung
    • Journal of the Korean Institute of Gas
    • /
    • v.19 no.4
    • /
    • pp.62-67
    • /
    • 2015
  • In this paper, the consequence analysis has been evaluated for the damage effects of the LPG storage tanks when they are installed on the ground or underground. They should be performed to identify measures to reduce risks for the LPG storage tanks which are more widely used. In order to conduct a damage effect evaluation of the LPG storage tanks installed underground, FDS was used to simulate the LPG storage tanks installed and housed within a facility. The maximum pressure of the storage facilities for the LPG storage tanks has been calculated from the FDS, and it's results are used as an input variable for Phast which is a commercial software for evaluating the damage effects. Getting results from the consequence analysis and computational simulations(diffusion range of LFL and UFL, jet fire or explosions) were quantitatively presented for the damage effects.

Determination of Self-Disposal date by the Analysis of Radioactive Waste Contamination for 1131I Therapy Ward (131I 치료입원실 폐기물 방사능 오염도 분석 및 자체처분가능일자 산출)

  • Kim, Gi-sub;Jung, Haijo;Park, Min-seok;Jeon, Gjin-seong
    • The Korean Journal of Nuclear Medicine Technology
    • /
    • v.17 no.1
    • /
    • pp.3-6
    • /
    • 2013
  • Purpose: The treatment of thyroid cancer patients was continuously increased. According to the increment of thyroid cancer patients, the establishment of iodine therapy site was also increased in each hospital. This treatment involves the administration of radioactive iodine, which will be given in the form of a capsule. Therefore, protections and managements for radioactive source pollution and radiation exposure should be necessary for radiation safety. Among the many problems, the problem of disposing the radioactive wastes was occurred. In this study, The date for self-disposal for radioactive wastes, which were contaminated in clothes, bedclothes and trash, were calculated. Materials and Methods: The number of iodine therapy ward was 15 in Korea Institute of Radiological Medical and Sciences. Recently, 8 therapy wards were operated for iodine therapy patients and others were on standby for emergency treatment ward of any radiation accidents. Radioactive wastes, which were occurred in therapy ward, were clothes, bedclothes, bath cover for patients washing water and food and drink which was leftover by patients. Each sample was hold into the marinelli beaker (clothes, bedclothes, bath covers) and 90 ml beaker (food, drink, and washing water). The activities of collected samples were measured by HpGe MCA device (Multi Channel Analysis, CANBERRA, USA) Results: The storage period for the each kind of radioactive wastes was calculated by equation of storage periods based on the measurement outcomes. The average storage period was 60 days for the case of clothes, and the maximum storage period was 93 days for patient bottoms. The average storage period and the maximum storage period for the trash were 69 days and 97 days, respectively. The leftover foods and drinks had short storage period (the average storage period was 25 days and maximum storage period was 39 days), compared with other wastes. Conclusion: The proper storage period for disposing the radioactive waste (clothes, bedclothes and bath cover) was 100 days by the regulation on self-disposal of radioactive waste. In addition, the storage period for disposing the liquid radioactive waste was 120 days. The current regulation for radioactive waste self-disposing was not suitable for the circumstances of each radioactive therapy facility. Therefore, it was necessary to reduce the leftover food and drinks by adequate table setting for patients, and improve the process and regulation for disposing the short-half life radioactive wastes.

  • PDF

Job Analysis of Food Safety Specialist Based on the Developing A Curriculum(DACUM) Method (DACUM(Developing A Curriculum)을 이용한 식품 안전 전문가 직무 분석)

  • Song, Tae-Hee
    • The Korean Journal of Food And Nutrition
    • /
    • v.22 no.1
    • /
    • pp.123-131
    • /
    • 2009
  • The purpose of this study was to define the job description for food safety specialist, and to describe the duties and tasks of the job based on the detailed analysis of specific food safety work performed by dietitians. The job analysis was 8 professional panels and a Developing A Curriculum(DACUM) facilitator. The research was done in order to fully define the task element, process, and sequence of a food specialist and was completed by DACUM analysis. The job definition of food safety specialist is one who manages food safety through analysis, safety evaluation, inspection, and hazard blocking in all processes related to the purchase, distribution, storage, manufacture, and marketing of foods and food materials. The job description on the DACUM research chart for food safety specialist contained 7 duties and 79 tasks. Its duties were defined as the specific and independent work of a food safety specialist, and were composed of 7 duties, i.e. hazard analysis of foods and related affairs, safety evaluation of purchased food materials, safety management of food/food materials distribution/storage, safety management of food manufacture, safety examination of food marketing, administration affairs on food safety, and self-development. For the future, this study suggests a curriculum, that shall be basis of program planning and food safety operation for subjects within many schools.

Changes in Quality of Expired Tofu During Storage at Different Temperatures (유통기한이 경과된 포장두부의 저장온도에 따른 품질변화)

  • Kim, Su-jin;Kim, Se-Hun;Bang, Woo-Suk
    • Journal of Food Hygiene and Safety
    • /
    • v.37 no.2
    • /
    • pp.80-86
    • /
    • 2022
  • The purpose of this study was to examine the microbiological and physicochemical changes on packaged tofu stored at temperatures of 5, 13, 23, and 30℃, and measure the consumable period from the expiry date to ultimately evaluate the microbiological safety on the extension of the consumable period. From the investigation, the pH value of tofu at each storage temperature (5, 13, and 23℃) showed a slight decrease over the storage period, although there was no significant change. The hardness of packaged tofu decreased more rapidly as temperature and storage time increased and the tofu started to show signs of decomposition at the same time. Analysis on the microbial change of tofu at different storage temperature revealed that the number of general bacteria also increased as the temperature increased. It was further found that packaged tofu takes 25 days at 5℃, 7 days at 13℃, and 1 day at 23℃ from the expiry date until the general bacteria count is at least at the early decomposition level which is 10℃ log CFU/g. However, no coliform bacteria was detected from tofu after storing at 5, 13 and 23℃. When packaged tofu was stored at 5℃, the L value changed significantly after 26 days, whereas the a and b values showed no significant change during the storage period (P>0.05). When storing tofu at 13℃ and 23℃ the L value decreased after 8 and 3 days, respectively. However, both a and b values increased (P<0.05).

EXTENDED DRY STORAGE OF USED NUCLEAR FUEL: TECHNICAL ISSUES: A USA PERSPECTIVE

  • Mcconnell, Paul;Hanson, Brady;Lee, Moo;Sorenson, Ken
    • Nuclear Engineering and Technology
    • /
    • v.43 no.5
    • /
    • pp.405-412
    • /
    • 2011
  • Used nuclear fuel will likely be stored dry for extended periods of time in the USA. Until a final disposition pathway is chosen, the storage periods will almost definitely be longer than were originally intended. The ability of the important-tosafety structures, systems, and components (SSCs) to continue to meet storage and transport safety functions over extended times must be determined. It must be assured that there is no significant degradation of the fuel or dry cask storage systems. Also, it is projected that the maximum discharge burnups of the used nuclear fuel will increase. Thus, it is necessary to obtain data on high burnup fuel to demonstrate that the used nuclear fuel remains intact after extended storage. An evaluation was performed to determine the conditions that may lead to failure of dry storage SSCs. This paper documents the initial technical gap analysis performed to identify data and modeling needs to develop the desired technical bases to ensure the safety functions of dry stored fuel.

Identification of Hazard for Securing the Safety of Unmanned Parcel Storage Device System Using Robot Technology

  • Park, Jae Min;Kim, Young Min
    • International Journal of Internet, Broadcasting and Communication
    • /
    • v.14 no.4
    • /
    • pp.132-139
    • /
    • 2022
  • The development of the fourth industrial revolution and logistics 4.0 related technology, the growth of the e-commerce market, and the transition to a non-face to face society due to the pandemic are accelerating the growth of the logistics industry. Due to the growth of the logistics industry, various services are emerging to meet the requirements of the market, and research and technology development related to the parcel storage, which is an important element of the last mile service, is also underway. In the past, if it was difficult to deliver the goods directly to the recipient, the parcel storage installed near the delivery location was used, but the usability was not good and the storage of the goods was limited. In addition, the existing parcel storage has a lot of functional limitations compared to the advanced logistics technology, so it is necessary to develop a device that improves it. Therefore, this study conducted to secure safety for unmanned parcel storage devices with robot technology to improve usability and functionality in line with the advanced logistics industry. Based on ISO 10218, an industrial robot related standard, risk identification studies were conducted to derive results that contribute to the development of devices under development.

Review on Spent Nuclear Fuel Performance and Degradation Mechanisms under Long-term Dry Storage (사용후핵연료의 장기 건식 건전성 성능과 주요 열화 기구에 관한 고찰)

  • Kim, Juseong;Kook, Donghak;Sim, Jeehyung;Kim, Yongsoo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.11 no.4
    • /
    • pp.333-349
    • /
    • 2013
  • As the capacity of spent nuclear fuel storage pool at reactor sites becomes saturated in ten years, long term dry storage strategy has been recently discussed as an alternative option in Korea. In this study, we reviewed safety-criteria-related research results on spent nuclear fuel performance and integrity under long-term dry storage and proposed the direction and the scope of future domestic research and development. Creep and hydride effect in relation to the embrittlement are known to be the major degradation mechanisms of the spent fuels during the long term dry storage. However, recent research results showed that hydride reorientation and hydride embrittlement are one of the most critical factors to the spent fuel integrity. Accordingly safety criteria of US and Japan for the storage system are basically founded on those mechanisms. However, in Korea, not only in-pile but out-of-pile experimental data have not been generated to understand fuel cladding degradation and to determine the criteria to ensure the safety. In addition, the transient behavior of the spent fuel during transportation also needs to be thoroughly examined. Therefore, various experimental research and development will be required to establish our own safety criteria for future long-term dry storage of domestic spent fuels.

Optimal Design of the Safety Valve by Response Surface Method (반응표면법을 이용한 안전밸브의 최적화)

  • Lee, Sang-Woo;Shin, Dae-Young;Byun, Cheol-Woong
    • Journal of the Computational Structural Engineering Institute of Korea
    • /
    • v.20 no.5
    • /
    • pp.551-556
    • /
    • 2007
  • High pressure storage of the agent gas in fire suppression system was composed of tank, main valve and safety valve, which prevents the fracture of the high pressure storage. The safety valve has circular thin plate as fracture plate that was destroyed over fracture pressure. When inner pressure of the storage is reached the fracture pressure, the safety valve discharges gas and degrades simultaneously the inner pressure of the storage. There are design variables such as flow path diameter, inner diameter of the plastic packing ring, thickness of plate and fillet radius. In this variables, thickness of plate is set to be a value of 0.2mm. The main effect of variables on the inner pressure, has been decided using factorial design and statistical analysis. Therefore, the relation of variables are expressed by regression equation. It is disclosed results that the difference of fracture pressures between the equation and experiment has $2{\sim}5%$. Finally, using response surface method, the optimal design of the safety valve could be decided with safety pressure of 25MPa, where the fracture occurs on circular thin plate.

A Safety Assessment for 140,000kl $9\%$ Ni Steel Type LNG Storage Tank (140,000kl $9\%$니켈강식 액화천연가스 저장탱크의 안전성 평가)

  • Lee Su Kyung,;Yang Byung Dong,
    • Journal of the Korean Institute of Gas
    • /
    • v.8 no.3 s.24
    • /
    • pp.57-62
    • /
    • 2004
  • This study is to assess the safety of the process facilities and fire fighting facilities for LNG storage tank which is the main facility in the LNG receiving terminal. The LNG storage tank(capacity : 140,000kl, type : aboveground, inner tank $9\%$ Ni steel plate, outer tank : prestressed concrete) was designed by foreign country up to now, but it has designed by domestic technology as the fifth in the world is under construction now.

  • PDF

Thermal-Hydraulic Analysis of Pipeline Transport System for Marine Geological Storage of Carbon Dioxide (이산화탄소 해양지중저장 처리를 위한 파이프라인 수송시스템의 열-유동 해석)

  • Huh, Cheol;Kang, Seong-Gil;Hong, Sup;Choi, Jong-Su;Baek, Jong-Hwa
    • Journal of Ocean Engineering and Technology
    • /
    • v.22 no.6
    • /
    • pp.88-94
    • /
    • 2008
  • The concentration of atmospheric carbon dioxide (CO2), which is one of the major greenhouse gases, continues to rise with the increase in fossil fuel consumption. In order to mitigate global warming the amount of CO2 discharge to the atmosphere must be reduced. Carbon dioxide capture and storage (CCS) technology is now regarded as one of the most promising options. To complete the carbon cycle in a CCS system, a huge amount of captured CO2 from major point sources such as power plantsshould be transported for storage into the marine or ground geological structures. Since 2005, we have developed technologies for marine geological storage of CO2,including possible storage site surveys and basic design of CO2 transport and storage process. In this paper, the design parameters which will be useful to construct on-shore and off-shore CO2 transport systems are deduced and analyzed. To carry out this parametric study, we suggested variations in thedesign parameters such as flow rate, diameter, temperature and pressure, based on a hypothetical scenario. We also studied the fluid flow behavior and thermal characteristics in a pipeline transport system.