• 제목/요약/키워드: Radiation Emergency

검색결과 224건 처리시간 0.019초

Cohort-based evacuation time estimation using TSIS-CORSIM

  • Park, Sunghyun;Sohn, Seokwoo;Jae, Moosung
    • Nuclear Engineering and Technology
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    • 제53권6호
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    • pp.1979-1990
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    • 2021
  • Evacuation Time Estimate (ETE) can provide decision-makers with a likelihood to implement evacuation of a population with radiation exposure risk by a nuclear power plant. Thus, the ETE is essential for developing an emergency response preparedness. However, studies on ETE have not been conducted adequately in Korea to date. In this study, different cohorts were selected based on assumptions. Existing local data were collected to construct a multi-model network by TSIS-CORSIM code. Furthermore, several links were aggregated to make simple calculations, and post-processing was conducted for dealing with the stochastic property of TSIS-CORSIM. The average speed of each cohort was calculated by the link aggregation and post-processing, and the evacuation time was estimated. As a result, the average cohort-based evacuation time was estimated as 2.4-6.8 h, and the average clearance time from ten simulations in 26 km was calculated as 27.3 h. Through this study, uncertainty factors to ETE results, such as classifying cohorts, degree of model complexity, traffic volume outside of the network, were identified. Various studies related to these factors will be needed to improve ETE's methodology and obtain the reliability of ETE results.

Development of a radiological emergency evacuation model using agent-based modeling

  • Hwang, Yujeong;Heo, Gyunyoung
    • Nuclear Engineering and Technology
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    • 제53권7호
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    • pp.2195-2206
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    • 2021
  • In order to mitigate the damage caused by accidents in nuclear power plants (NPPs), evacuation strategies are usually managed on the basis of off-site effects such as the diffusion of radioactive materials and evacuee traffic simulations. However, the interactive behavior between evacuees and the accident environment has a significant effect on the consequential gap. Agent-based modeling (ABM) is a method that can control and observe such interactions by establishing agents (i.e., the evacuees) and patches (i.e., the accident environments). In this paper, a radiological emergency evacuation model is constructed to realistically check the effectiveness of an evacuation strategy using NetLogo, an ABM toolbox. Geographic layers such as radiation sources, roads, buildings, and shelters were downloaded from an official geographic information system (GIS) of Korea, and were modified into respective patches. The dispersion model adopted from the puff equation was also modified to fit the patches on the geographic layer. The evacuees were defined as vehicle agents and a traffic model was implemented by combining the shortest path search (determined by an A * algorithm) and a traffic flow model incorporated in the Nagel-Schreckenberg cellular automata model. To evaluate the radiological harm to the evacuees due to the spread of radioactive materials, a simple exposure model was established to calculate the overlap fraction between the agents and the dispersion patches. This paper aims to demonstrate that the potential of ABM can handle disaster evacuation strategies more realistically than previous approaches.

Planning and decommissioning of a disused Theratron- 780 teletherapy machine and the dose assessment methodology for normal and radiological emergency conditions

  • Mohamed M.Elsayed Breky ;Muhammad S. Mansy;A.A. El-Sadek ;Yousif M. Mousa ;Yasser T. Mohamed
    • Nuclear Engineering and Technology
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    • 제55권1호
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    • pp.238-247
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    • 2023
  • The present work represents a technical guideline for decommissioning a disused teletherapy machine model Theratron-780 and contains category one 60Co radioactive source. The first section predicts the dose rate from the source in case of normal and radiological emergency situations via FLUKA-MC simulation code. Moreover, the dose assessment for the occupational during the whole process is calculated and compared to the measured values. A suggested cordoned area for safety and security in a radiological emergency is simulated. The second section lists the whole process's technical procedures, including (preview, dismantle, securing, transport and storage) of the disused teletherapy machine. Results show that the maximum obtained accumulated dose for occupational were found to be 24.5 ± 4.9 μSv in the dismantle and securing process in addition to 3.5 ± 1.8 μSv during loading on the transport vehicle and unloading at the storage facility. It was found that the measured accumulated dose for workers is in good agreement with the estimated one by uncertainty not exceeding 5% in normal operating conditions.

Gastrointestinal Emergency in Neonates and Infants: A Pictorial Essay

  • Gayoung Choi;Bo-Kyung Je;Yu Jin Kim
    • Korean Journal of Radiology
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    • 제23권1호
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    • pp.124-138
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    • 2022
  • Gastrointestinal (GI) emergencies in neonates and infants encompass from the beginning to the end of the GI tract. Both congenital and acquired conditions can cause various GI emergencies in neonates and infants. Given the overlapping or nonspecific clinical findings of many different neonatal and infantile GI emergencies and the unique characteristics of this age group, appropriate imaging is key to accurate and timely diagnosis while avoiding unnecessary radiation hazard and medical costs. In this paper, we discuss the radiological findings of essential neonatal and infantile GI emergencies, including esophageal atresia and tracheoesophageal fistula, hypertrophic pyloric stenosis, duodenal atresia, malrotation, midgut volvulus for upper GI emergencies, and jejunoileal atresia, meconium ileus, meconium plug syndrome, meconium peritonitis, Hirschsprung disease, anorectal malformation, necrotizing enterocolitis, and intussusception for lower GI emergencies.

A detector system for searching lost γ-ray source

  • Khan, Waseem;He, Chaohui;Cao, Yu;Khan, Rashid;Yang, Weitao
    • Nuclear Engineering and Technology
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    • 제52권7호
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    • pp.1524-1531
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    • 2020
  • The aim of this work is to develop a Geiger-Muller (GM) detector system for robot to look for a radioactive source in case of a nuclear emergency or in a high radiation environment. In order to find a radiation source easily, a detector system, including 3 detectors, was designed to search γ-ray radiation sources autonomously. First, based on GEANT4 simulation, radiation dose rates in 3 Geiger-Muller (GM) counters were simulated at different source-detector distances, distances between detectors and angles. Various sensitivity analyses were performed experimentally to verify the simulated designed detector system. A mono-energetic 137Cs γ-ray source with energy 662 keV and activity of 1.11 GBq was used for the observation. The simulated results were compared with the experimental dose rate values and good agreements were obtained for various cases. Only based on the dose rates in three detectors, the radiation source with a specific source activity and angle was localized in the different location. A method was adopted with the measured dose rates and differences of distances to find the actual location of the lost γ-ray source. The corresponding angles of deviation and detection limits were calculated to determine the sensitivity and abilities of our designed detector system. The proposed system can be used to locate radiation sources in low and high radiation environments.

월성 원자력 발전소 2,3,4호기에서의 LOCA 사고후 보조건물의 방사선장 평가 (Assessment of Post-LOCA Radiation Fields in Service Building Areas for Wolsong 2, 3, and 4 Nuclear Power Plants)

  • 진영권;김용일
    • Journal of Radiation Protection and Research
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    • 제20권1호
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    • pp.53-64
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    • 1995
  • 월성 원자력발전소 2,3,4 호기의 보조건물 주요 지역에서 냉각재 다량상h7사고 (large LOCA) 후의 방사선장을 평가하였다. 핵분열 생성물의 총량은 ORIGEN2 코드를 사용하여 계산하였고 선원항은 2중고장 시나리오, 즉 LOCA 사고후 비상노심냉각 (ECC) 계통의 고장이 결부된 사고시의 방사능 방출에 근거하였다. 원자로건물, 보조건물 및 ECC 계통의 구조모형을 QAD-CG 모델에 포함하여 계산하였다. 사고시점부터 90일 경과시까지 시간대 별로 선량율과 누적선량을 계산하였다. 결과적으로, 연속출입이 요구되는 중요지역에서의 방사선장은 충분히 낮은 것으로 평가되었다. 그러나, 일부구역에서는 제한적인 출입을 허용할 정도로 상대적으로 높은 방사선장을 나타내었다.

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방사능 방호 제품에 대한 KOLAS 인증 방안 연구 - 마스크를 중심으로 (Study on KOLAS Certification Approach for Radiation Protection Products - Focusing on Masks)

  • 박남희;여욱현;홍성진
    • 한국재난정보학회 논문집
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    • 제19권4호
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    • pp.815-825
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    • 2023
  • 연구목적: 본 논문은 방사선비상계획구역 내 거주하는 주민의 방사능재난 발생시 대피과정에서 사용할 수 있는 방호제품으로서 마스크를 개발하는 과정에서 KOLAS 인증을 받을 수 있는 방안을 연구하는 것이다. 연구방법: 각종 보고서와 논문, KOLAS 인정기구 및 각종 마스크 홈페이지 자료를 조사하여 연구하였다. 연구결과: 국내 방사능재난방재대책을 수립하여 주민보호조치를 강화하고 있으나 방호제품 보급은 갑상샘방호약품이 유일하다. 방사능재난에 대비하여 마스크와 같은 보조적인 지원용품 보급이 필요하다. 방호마스크를 공인인증할 수 있는 KOLAS 인정 공인기관이 없는 실정이다. 결론: 성능 인증 기준이 있는 마스크의 경우 산업용 방진마스크로 공인시험성적서를 발급받고 인증을 받은 후에 자체 기준으로 일반성적서를 받는 이중 과정을 거쳐서 마스크의 KOLAS 인증이 가능하다.

From Radon and Thoron Measurements, Inhalation Dose Assessment to National Regulation and Radon Action Plan in Cameroon

  • Saidou;Shinji Tokonami;Masahiro Hosoda;Augustin Simo;Joseph Victor Hell;Olga German;Esmel Gislere Oscar Meless
    • Journal of Radiation Protection and Research
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    • 제47권4호
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    • pp.237-245
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    • 2022
  • Background: The current study reports measurements of activity concentrations of radon (220Rn) and thoron (220Rn) in dwellings, followed by inhalation dose assessment of the public, and then by the development of regulation and the national radon action plan (NRAP) in Cameroon. Materials and Methods: Radon, thoron, and thoron progeny measurements were carried out from 2014 to 2017 using radon-thoron discriminative detectors (commercially RADUET) in 450 dwellings and thoron progeny monitors in 350 dwellings. From 2019 to 2020, radon track detectors (commercially RADTRAK) were deployed in 1,400 dwellings. It was found that activity concentrations of radon range in 1,850 houses from 10 to 2,620 Bq/㎥ with a geometric mean of 76 Bq/㎥. Results and Discussion: Activity concentrations of thoron range from 20 to 700 Bq/㎥ with a geometric mean of 107 Bq/㎥. Thoron equilibrium factor ranges from 0.01 to 0.6, with an arithmetic mean of 0.09 that is higher than the default value of 0.02 given by UNSCEAR. On average, 49%, 9%, and 2% of all surveyed houses have radon concentrations above 100, 200, and 300 Bq/㎥, respectively. The average contribution of thoron to the inhalation dose due to radon and thoron exposure is about 40%. Thus, thoron cannot be neglected in dose assessment to avoid biased results in radio-epidemiological studies. Only radon was considered in the drafted regulation and in the NRAP adopted in October 2020. Reference levels of 300 Bq/㎥ and 1,000 Bq/㎥ were recommended for dwellings and workplaces. Conclusion: Priority actions for the coming years include the following: radon risk mapping, promotion of a protection policy against radon in buildings, integration of the radon prevention and mitigation into the training of construction specialists, mitigation of dwellings and workplaces with high radon levels, increased public awareness of the health risks associated with radon, and development of programs on the scientific and technical aspects.

한국표준형 원전에 대한 방사선비상계획구역 범위 평가 (Evaluation of the Size of Emergency Planning Zone for the Korean Standard Nuclear Power Plants)

  • 전인영;이재기
    • Journal of Radiation Protection and Research
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    • 제28권3호
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    • pp.215-223
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    • 2003
  • 원자력발전소로부터의 만일의 방사성물질 누출사고에 대비해 원자력발전소 주변에는 주민보호조치를 효율적으로 수행하기 위해 비상계획구역이 설정되어 있다. 그러나 이러한 비상계획구역 크기를 결정하는 국내의 방법론은 보수적인 사고선원항을 이용하여 계산한 1980년에 발표된 일본의 이론에 근거하고 있다. 본 연구의 목적은 울진 3&4호기의 확률론적 안전성점검 연구결과로 얻어진 사고선원항을 토대로 현재 원전을 중심으로 반경 $8{\sim}10km$의 주변지역으로 설정되어 있는 방사선 비상계획구역의 적합성을 재평가하는 것이다. 방사선영향평가를 위해서 컴퓨터 코드인 MACCS2(MELCOR Accident Consequence Code System2)코드를 사용하였다. 연구결과는 현재 울진원전을 중심으로 설정되어 있는 반경 $8{\sim}10km$의 비상계획구역으로서 STC-14 및 STC-19를 제외한 대부분의 선원항들에 대해 조기사망 발생확률을 크게 낮출 수 있음을 보여주고 있다. STC-14의 경우는 16km 이상, STC-19의 경우는 13km이상 소개되어야 조기사망 발생확률이 현저하게 감소되었다. 주민보호조치에 대한 민감도 분석결과에서는 사고통보 및 소개와 관련된 시간지연이 조기사망효과에 대해 직접적이고도 매우 큰 영향을 주고 있음을 확인할 수 있었다.