• Title/Summary/Keyword: Chemical Accident

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A Study on the Improvement of Hazardous Materials Accident Report for Chemical Safety Management (화학물질 안전관리를 위한 위험물 사고 발생보고서 개선연구)

  • Goh, Moon-Soo;Jang, Hyeon-Jun;Seong, Chun-Mo;Lee, Hunggi;Lee, Bong-Woo;Shin, Dong-il
    • Journal of the Korean Institute of Gas
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    • v.26 no.1
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    • pp.41-49
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    • 2022
  • Chemicals are widely used throughout society, and usage is expected to increase in the future. As a result, various accidents related to chemicals and dangerous substances are occurring, and the frequency of occurrence is expected to continue to increase. Thus, it is expected that this study will present problems and improvement directions through analysis of each associated agency's accident report and management system, and improve the research input system to increase efficiency in collecting and statistical calculation of chemical and hazardous accident.

Risk Analysis of Ammonia Leak in the Refrigeration Manufacturing Facilities (냉동제조 시설의 암모니아 누출사고 위험 분석)

  • Kang, Su-Jin;Lee, Ik-Mo;Moon, Jin-Young;Chon, Young-Woo
    • Journal of the Korean Institute of Gas
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    • v.21 no.1
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    • pp.43-51
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    • 2017
  • Recently, ammonia leak occurred frequently in the domestic refrigeration manufacturing facilities. Ammonia caused great damage to the environment and human health in the event of an accident as combustible gases and toxic gases. After considering the types of ammonia accidents of domestic refrigeration manufacturing facilities and selected accident scenarios and to analyze the risk analysis through Impact range estimates and frequency analysis and there was a need to establish measures to minimize accident damage. In this study, depending on the method of analysis quantitative risk assessment we analyzed the risk of the receiver tank of ammonia system. Scenario analysis conditions were set according to the 'Technical guidelines for the selection of accident scenario' under the chemicals control act and 'Guidelines for chemical process quantitative risk analysis' of center for chemical process safety. The risk estimates were utilized for consequence analysis and frequency analysis by SAFETI program of DNV, event tree analysis methodology and part count methodology. The individual risk of ammonia system was derived as 7.71E-04 / yr, social risk were derived as 1.17E-03 / yr. The derived risk was confirmed to apply as low as reasonably practicable of the national fire protection association and through risk calculation, it can be used as a way to minimize accidents ammonia leakage accident damage.

An Empirical Analysis of the Industrial Accident Factors Affecting Manufacturing Performance in Korea

  • Park, Hai Chun;Kim, Jong Rae
    • International Journal of Safety
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    • v.2 no.1
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    • pp.45-49
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    • 2003
  • In this paper, we investigated the relationship between the variables of the industrial accident factors and the manufacturing performances such as production quantity, quality, cost, and delivery. For this investigation, we collected the real data from 30 small/medium-sized manufacturing industries by performing a questionnaire survey and a on-site inter-view with the workers. Thirty industries were made up of 10 from each of the following three industries: metal processing, machinery manufacturing, and chemical products manufacturing. The data analysis was made using SPSS PC+. Based on the result of the analysis, we came to the tentative conclusion that only two variables such as work skill and load affected all four manufacturing performances and the rest of them two or three performances.

Use of MAAP in Generating Accident Source Term Parameters

  • Kim, Jong-Wok;Yun, Joeng-Ik;Kang, Chang-Sun
    • Nuclear Engineering and Technology
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    • v.30 no.3
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    • pp.235-244
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    • 1998
  • The parametric model method determines the accident source term which is Presented by a set of source term parameters. In this method, the cumulative distribution of each source term parameter should be derived for its uncertainty analysis. This paper introduces a method of generating the parameters in the form of cumulative distribution using MAAP version 4.0. In MAAP, there are model parameters which could incorporate uncertain physical and/or chemical phenomena. In general, the model parameters do not have a point value but a range. In this paper, considering that, the input values of model parameters influencing each parameter are sampled using LHS. Then, the computation results are shown in cumulative distribution form. For a case study, the CDFs of FCOR and WES of Kori Unit 1 are derived. The target scenarios for the computation are the ones whose initial events are large LOCA, small LOCA and transient, respectively. It is found that the computed CDF's in this study are consistent to those of NUREG-1150 and the use of MAAP is proven to be adequate in assessing the parameters of the severe accident source term.

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MULTI-DIMENSIONAL APPROACHES IN SEVERE ACCIDENT MODELLING AND ANALYSES

  • Fichot, F.;Marchand, O.;Drai, P.;Chatelard, P.;Zabiego, M.;Fleurot, J.
    • Nuclear Engineering and Technology
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    • v.38 no.8
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    • pp.733-752
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    • 2006
  • Severe accidents in PWRs are characterized by a continuously changing geometry of the core due to chemical reactions, melting and mechanical failure of the rods and other structures. These local variations of the porosity and other parameters lead to multi-dimensionnal flows and heat transfers. In this paper, a comprehensive set of multi-dimensionnal models describing heat transfers, thermal-hydraulics and melt relocation in a reactor vessel is presented. Those models are suitable for the core description during a severe accident transient. A series of applications at the reactor scale shows the benefits of using such models.

Development of a Supporting Program for the Emergency Preparedness Plan (사고대비물질 취급자의 비상대응계획 작성 프로그램 연구)

  • Kim, Sung-Bum;Noh, Hye-Ran;Seok, Gwang-Seol;Park, Jae-Deuk
    • Journal of the Korean Society of Safety
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    • v.26 no.5
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    • pp.54-58
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    • 2011
  • Emergency preparedness plan(EPP) is the systematic management of activities that involve a material degree of risk of loss or other damage to the surroundings(people, property and environment), and the boundary of accident recovery plan(ARP). The main purpose of the program is to provide a safety management system to each facility in order to enable to prevent accident and to control accident immediately. The EPP includes not only typical safety-related documentations such as material safety data sheet(MSDS), standard operation procedure(SOP), emergency response plan(ERP). EPP is established basis of the preliminary safety analysis involving risk identification, assessment and prevention plans. The program is also helpful for government or related agencies to control a number of accidents in small-scale companies in the whole country.

Analysis of Explosion Energy related to the Cause of Tianjin Explosion Accident in China (중국 텐진항 폭발사고 원인과 관련된 폭발 에너지 분석)

  • Kwon, Sangki;Kim, Ha Yung
    • Explosives and Blasting
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    • v.34 no.1
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    • pp.1-10
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    • 2016
  • On August 12, 2015, two huge explosions were accidently happened in Tianjin port, China. The explosion energies of the two explosions were similar to those of TNT 3 tons and TNT 21 tons. Until now, the cause of the explosions was not clearly announced but some guesses of the cause were released. One of the possible cause of the explosion is the generation of explosive acetylene gas from the chemical reaction between $CaC_2$ and spraying water to extinguish fire happened at the storage site of different chemical compounds. The explosion of acetylene gas might ignite the explosion of 800 tons of ammonium nitrate. In this study, the explosion due to the scenario was analyzed in order to check that such a chemical reaction can produce the huge explosion observed at the Tianjin accident.

The corrosion of aluminium alloy and release of intermetallic particles in nuclear reactor emergency core coolant: Implications for clogging of sump strainers

  • Huang, Junlin;Lister, Derek;Uchida, Shunsuke;Liu, Lihui
    • Nuclear Engineering and Technology
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    • v.51 no.5
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    • pp.1345-1354
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    • 2019
  • Clogging of sump strainers that filter the recirculation water in containment after a loss-of-coolant accident (LOCA) seriously impedes the continued cooling of nuclear reactor cores. In experiments examining the corrosion of aluminium alloy 6061, a common material in containment equipment, in borated solutions simulating the water chemistry of sump water after a LOCA, we found that Fe-bearing intermetallic particles, which were initially buried in the Al matrix, were progressively exposed as corrosion continued. Their cathodic nature $vis-{\grave{a}}-vis$ the Al matrix provoked continuous trenching around them until they were finally released into the test solution. Such particles released from Al alloy components in a reactor containment after a LOCA will be transported to the sump entrance with the recirculation flow and trapped by the debris bed that typically forms on the strainer surface, potentially aggravating strainer clogging. These Fe-bearing intermetallic particles, many of which had a rod or thin strip-like geometry, were identified to be mainly the cubic phase ${\alpha}_c-Al(Fe,Mn)Si$ with an average size of about $2.15{\mu}m$; 11.5 g of particles with a volume of about $3.2cm^3$ would be released with the dissolution of every 1 kg 6061 aluminium alloy.

Toxic Concentration(T-LOC) Endpoint Distance Study for Fire Brigade Protection in Response to Chemical Accidents (화학사고 초기대응 소방대 보호를 위한 독성농도(T-LOC) 끝점거리 연구)

  • Jong Chan Yun;Chul Hee Cho;Jeong Hun Won
    • Journal of the Korean Society of Safety
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    • v.38 no.6
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    • pp.60-71
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    • 2023
  • The purpose of this study is to propose a quantitative toxicity endpoint distance suitable for the initial response of firefighters by comparing and analyzing the commonly applied toxic level of concern (T-LOC), specifically emergency response planning guidelines (ERPG), acute exposure guideline levels (AEGL), and immediately dangerous to life or health (IDLH). This is to protect the fire brigade, which responds to toxic chemical accidents first during the golden time. Using areal locations of hazardous atmospheres, a damage prediction program, the amount of leakage for both acidic and basic substances, along with the endpoint distance, were analyzed for alternative accident and worst-case accident scenarios. The results showed that the toxicity endpoint distance, serving as a compromise between Level-3 and Level-2 of T-LOC, was longer than ERPG-3 and shorter than ERPG-2 with IDLH, while its values were analyzed in the order of ERPG-2, AEGL-2, IDLH, AEGL-3, and ERPG-3. It is suggested that the application of IDLH in an emergency (red card) and ERPG-2 endpoint distance in a non-emergency (non-red card) can be utilized for the initial response of the fire brigade.

An analytical model to decompose mass transfer and chemical process contributions to molecular iodine release from aqueous phase under severe accident conditions

  • Giedre Zablackaite;Hiroyuki Shiotsu;Kentaro Kido;Tomoyuki Sugiyama
    • Nuclear Engineering and Technology
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    • v.56 no.2
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    • pp.536-545
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    • 2024
  • Radioactive iodine is a representative fission product to be quantified for the safety assessment of nuclear facilities. In integral severe accident analysis codes, the iodine behavior is usually described by a multi-physical model of iodine chemistry in aqueous phase under radiation field and mass transfer through gas-liquid interface. The focus of studies on iodine source term evaluations using the combination approach is usually put on the chemical aspect, but each contribution to the iodine amount released to the environment has not been decomposed so far. In this study, we attempted the decomposition by revising the two-film theory of molecular-iodine mass transfer. The model involves an effective overall mass transfer coefficient to consider the iodine chemistry. The decomposition was performed by regarding the coefficient as a product of two functions of pH and the overall mass transfer coefficient for molecular iodine. The procedure was applied to the EPICUR experiment and suppression chamber in BWR.