• Journal of Radiation Protection and Research
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• 제42권2호
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• pp.114-129
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• 2017

Background: The purpose of this paper is to confirm the event timings and the magnitude of fission product aerosol release from the Fukushima accident. Over a few hundreds of technical papers have been published on the environmental impact of Fukushima Daiichi accident since the accident occurred on March 11, 2011. However, most of the research used reverse or inverse method based on the monitoring of activities in the remote places and only few papers attempted to estimate the release of fission products from individual reactor core or from individual spent fuel pool. Severe accident analysis code can be used to estimate the radioactive release from which reactor core and from which radionuclide the peaks in monitoring points can be generated. Materials and Methods: The basic material used for this study are the initial core inventory obtained from the report JAEA-Data/Code 2012-018 and the given accident scenarios provided by Japanese Government or Tokyo Electric Power Company (TEPCO) in official reports. In this research a forward method using severe accident progression code is used as it might be useful for justifying the results of reverse or inverse method or vice versa. Results and Discussion: The release timing and amounts to the environment are estimated for volatile radioactive fission products such as noble gases, cesium, iodine, and tellurium up to 184 hours (about 7.7 days) after earthquake occurs. The in-plant fission product behaviors and release characteristics to environment are estimated using the severe accident progression analysis code, MELCOR, for Fukushima Daiichi accident. These results are compared with other research results which are summarized in UNSCEAR 2013 Report and other technical papers. Also it may provide the physically based arguments for justifying or suspecting the rationale for the scenarios provided in open literature. Conclusion: The estimated results by MELCOR code simulation of this study indicate that the release amount of volatile fission products to environment from Units 1, 2, and 3 cores is well within the range estimated by the reverse or inverse method, which are summarized in UNSCEAR 2013 report. But this does not necessarily mean that these two approaches are consistent.

• 한국가스학회지
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• 제16권4호
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• pp.44-51
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• 2012

대부분의 산업시설이 유해물질을 다루고 있기 때문에 산업시설의 사고발생은 막대한 물적, 인적 피해를 발생시키므로 안전관리, 중대형 사고 예방 및 위험 예측 등이 중요시 되고 있다. 특히, 유해물질 누출사고는 누출물질, 저장시설, 대기 상태에 따라 유독가스의 확산 속도와 범위가 달라지므로 이를 모사하는 대기확산 시스템이 이용되어왔다. 모사에 기반하는 대기확산 시스템은 산업시설 구조물 설계 단계에서 주로 사용되며 누출 사고 시 즉각적인 처리와 대응이 어렵다. 실시간 대기정보 데이터를 이용한 연구 및 사례는 존재하지만 시스템의 성능저하 및 전문적 지식의 결여로 신속한 처리 및 대응이 미흡하였다. 본 논문은 에너지 플랜트 환경에서 특수성과 효율성을 강화하여 유해화학물질 누출로 인한 대기확산범위를 즉각적으로 산출하고 누출 시점 및 지점을 지능형 알고리즘으로 결정함으로써 사고예방형 실시간 지능형 대기확산 시스템을 구현한다.

• 한국화재소방학회:학술대회논문집
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• 한국화재소방학회 1996년도 학술발표회
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• pp.53-56
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• 1996

In order to propose the method of the consequence analysis for fire accidents by the heavy gas release and to obtain optimum conditions of parameter selections, the consequence analysis for jet fire by the accident of xylene vapor release were performed. And the effect and the sensitivity analysis of parameters affecting the consequence were investigated. Simulation results showed that important parameters affecting results of the xylene vapor release accident were mainly hole diameter, interested distance, wind speed, and so on. For the jet fire, the accident result and the sensitivity of thermal radiation were increased with the decrease of interested distance and the increase of hole diameters, and the accidental result was increased as the increase wind speed, but the sensitivity of thermal radiation was decreased.

• 대한안전경영과학회지
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• 제8권6호
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• pp.29-39
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• 2006

The effect of parameters on the consequence of the flash fire accident by the release of heavy gas(in this study, xylene vapor) was analyzed. Simulation results showed that the distance with the lower flammable limit($X_{LFL}$) was increased with the increase of the release hole diameter. For the case of the elevated release, $X_{LFL}$ was increased with the increase of the wind speed and the release height, but $X_{LFL}$ was not affected by the wind speed for the release on the ground level. Therefore, the accident in the elevated release was more dangerous than the release on the ground level. In this condition, the release height had more effect on $X_{LFL}$ at the night time than the daytime and in the urban area than the rural area.

• 대한안전경영과학회지
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• 제4권3호
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• pp.35-43
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• 2002

For the unconfined vapor cloud explosion accident by the continuous release of gas-liquid flow of various saturated liquids in a vessel at ground level, overpressures were estimated and analyzed with various release conditions and materials by TNT equivalency model with vapor dispersion. We found that at same release conditions, overpressure showed n-heptane > xylene > n-hexane > toluene > n-heptane > benzene, respectively and that overpressure was increased with increasing the hole diameter and the storage pressure, but it was increased with decreasing the wind speed, the interested distance, and the vessel thickness.

• Nuclear Engineering and Technology
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• 제53권3호
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• pp.812-824
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• 2021

In order to reduce risks from the Steam Generator Tube Rupture (SGTR) accident and to meet safety targets, various measures have been analyzed to minimize the amount of fission product (FP) release. In this paper, we propose an introduction of a Containment Filtered Venting System (CFVS) connected to the steam generator secondary side, which can reduce the amount of FP release while minimizing adverse effects identified in the previous studies. In order to compare the effect of new equipment with the existing strategy, accident simulations using MELCOR were performed. As a result of simulations, it is confirmed that CFVS operation lowers FP release into the environment, and the release fractions are lower (minimum 0.6% of the initial inventory for Cs) than that of the strategy which intends to depressurize the primary system directly (minimum 15.2% for Cs). The sensitivity analyses identify that refill of the CFVS vessel is a dominant contributor reducing the amount of FP released. As the new strategy has the possibility of hydrogen combustion and detonation in CFVS, the installation of an igniter inside the CFVS vessel may be considered in reducing such hydrogen risk.

• 한국안전학회지
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• 제18권1호
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• pp.64-70
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• 2003

For the unconfined vapor cloud explosion(UVCE) accident by the continuous release of gas-liquid flow of various saturated liquids in a vessel at ground level, overpressures were estimated by TNT equivalency model with two estimation methods, such as UVCE I model based on a constant release time and UVCEII model based on a real travel time of vapor by dispersion and analyzed with various release conditions. As a simulation result the simple, easy, and correct method of evaluation of consequences of the UVCE accident was proposed by using consequences of UVCE I model and correlation equations for differences of overpressures between UVCE models, so that this evaluation method could be used easily in the small and medium size enterprises without using the dispersion model.

• 한국가스학회지
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• 제9권2호
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• pp.43-49
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• 2005

현재 여러 가지 목적으로 사용되고 있는 독성가스는 누출사고 발생시 확산되는 특성이 있어 피해 범위가 매우 넓고, 인체에 치명적이라는 특징을 가지고 있다. 따라서, 위험성이 높은 독성가스 이용시설은 누출사고에 대비한 사고 대응 시스템을 구축하여 비상상황 발생시 즉각 대응이 가능하도록 하여야 한다. 이에 본 연구에서는 FTA기법을 이용한 사고 시나리오 선정 및 빈도 분석과 DNV사의 PHAST(Ver 6.2)를 이용하여 독성가스 누출에 의한 확산 사고영향 분석을 실시하였다. 그리고, 정량적 위험성 평가 결과들을 이용하여 독성가스시설의 비상대응시스템을 구축하였다.

• 한국가스학회지
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• 제20권5호
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• pp.104-111
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• 2016

최근 화학물질을 사용하는 시설이 증가하면서 동시에 시설의 노후화, 기계적 결함, 인적오류 등으로 화학물질 누출사고 피해가 많아지고 있다. 특히, 산업단지는 군집 특성으로 인해 화학물질 누출사고 발생 시 인근 사업장으로 확산되어 큰 피해로 이어질 가능성이 크다. 이에 따라 화학물질을 취급하는 공정의 누출조건, 환경조건을 반영한 다양한 누출 시나리오를 토대로 빠른 감지와 대응을 위해 경계면의 센서배치 방안을 제시할 필요가 있다. 따라서 본 연구에서는 염소가스가 누출되는 경우에 대해 COMSOL를 사용하여 주요 매개변수의 적용으로 실질적인 사고 시나리오를 해석하였다. 그리고 사고 시나리오를 바탕으로, 센서의 감지 확률과 감지시간 등 각 항목마다 중요도를 부여하여 최적 위치가 산출되도록 목적함수를 선정하였다. 또한 예상치 못한 지역의 누출사고에 대해 최적화된 센서배치의 강건성 분석을 통해 본 방안의 타당성을 높였다. 결과적으로, 기존 방식보다 효과적으로 경계면의 센서배치 최적화 방법의 적용 가능성을 확인하였다. 이상의 결과로 부터 이동식 센서의 배치방법과 농도 데이터를 기반으로, 누출원의 역추적에 도움을 줄 수 있을 것으로 기대한다.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2690-2701
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• 2022

In this paper, we select important fission products for the estimation of the source term during a severe accident of a PWR. The selection is based on the numerical results obtained from depletion calculations for the typical PWR fuel via the in-house code named DEGETION (Depletion, Generation, and Transmutation of Isotopes on Nuclear Application), release fractions of the fission products derived from NUREG-1465, and effective dose conversion coefficients from ICRP 119. Then, for the selected fission products, we obtain the adjoint solutions of the Bateman equations for radioactive decay in order to determine the importance of precursors producing the aforementioned fission products via radioactive decay, which would provide insights into the assumption used in MACCS 2 for a level 3 PSA analysis in which up to six precursors are considered in the calculations of radioactive decays for the fission product after release from the reactor.