• Journal of Radiation Protection and Research
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• 제41권3호
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• pp.301-309
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• 2016

Background: A contamination screening process for the local population in radiation emergencies is discussed. Materials and Methods: We present an overview of the relevant Korean governmental regulations that underpin the development of an effective response system. Moreover, case studies of foreign countries responding to mass casualties are presented, and indicate that responses should be able to handle a large demand for contamination screening of the local public as well as screening of the immediate victims of the incident. Results and Discussion: We propose operating procedures for an off-site contamination screening post operated by the local government for members of the public who have not been directly harmed in the accident. In order to devise screening categories, sorting strategies assessing contamination and exposure are discussed, as well as a psychological response system. Conclusion: This study will lead to the effective operation of contamination screening clinics if an accident occurs. Furthermore, the role of contamination screening clinics in the overall context of the radiation emergency treatment system should be clearly established.

• Nuclear Engineering and Technology
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• 제56권4호
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• pp.1213-1224
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• 2024

The liquid lead-bismuth cooled fast reactor has been in a single-phase, low-pressure, and high-temperature state for a long time during operation. Considering the requirement of calculation efficiency for long-term transient accident calculation, based on a homogeneous hydrodynamic model, one-dimensional heat conduction model, coolant flow and heat transfer model, neutron kinetics model, coolant and material properties model, this study used the fully implicit difference scheme algorithm of the convection-diffusion term to solve the basic conservation equation, to develop the transient analysis program NUSOL-LMR 2.0 for the lead-bismuth fast reactor system. The steady-state and typical design basis accidents (including reactivity introduction, loss of flow caused by main pump idling, excessive cooling, and plant power outage accidents) for the ABR have been analyzed. The results are compared with the international system analysis software ATHENA. The results indicate that the developed program can stably, accurately, and efficiently predict the transient accident response and safety characteristics of the lead-bismuth fast reactor system.

• Journal of Radiation Protection and Research
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• 제41권2호
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• pp.87-91
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• 2016

Background: A hand-held detector for an emergency response was developed for nuclide identification and to estimate the information of the ambient dose rate in the scene of an accident as well as the radioactivity of the contaminants. Materials and Methods: To achieve this, the most suitable sensor was first selected as a cadmium zinc telluride (CZT) semiconductor and the signal processing unit from a sensor and the signal discrimination and storage unit were successfully manufactured on a printed circuit board. Results and Discussion: The performance of the developed signal processing unit was then evaluated to have an energy resolution of about 14 keV at 662 keV. The system control unit was also designed to operate the CZT detector, monitor the detector, battery, and interface status, and check and transmit the measured results of the ambient dose rate and radioactivity. In addition, a collimator, which can control the inner radius, and the airborne dust sampler, which consists of an air filter and charcoal filter, were developed and mounted to the developed CZT detector for the quick and efficient response of a nuclear accident. Conclusion: The hand-held CZT detector was developed to make the in-situ gamma-ray spectrometry and its performance was checked to have a good energy resolution. In addition, the collimator and the airborne dust sampler were developed and mounted to the developed CZT detector for a quick and efficient response to a nuclear accident.

• 한국전자통신학회논문지
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• 제14권2호
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• pp.351-360
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• 2019

최근 정부의 에너지 정책에 힘입어 ESS(: Energy Storage System) 설비가 증가하고 있으며 이로 인해 화재 폭발 등 다양한 사건사고가 발생하고 있다. 현재 ESS는 PMS(: Power Management System) 포함하여 모든 시스템이 현장에 설치되어있는 통합형 ESS로 구축되어 있다. 이 시스템은 사고 발생 시 산화되어 데이터의 부재 가능성이 매우 높을 뿐만 아니라 외부에 존재하는 관리자가 사고 발생 시 신속하게 대응할 방법이 없는 상황이다. 이에 본 논문에서는 별도의 WAS 및 데이터 스토리지 구축을 통해 기존 시스템에서의 주요 기능을 분리하여 외부에서 EMS(: Energy Management system) 운용이 가능함과 동시에 사고 발생 시 원인 및 신속한 대응이 가능한 독립형 PMS 개발을 제안하고자 한다.

• Nuclear Engineering and Technology
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• 제45권6호
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• pp.767-790
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• 2013

MAAP4 is a computer code that can simulate the response of a light water reactor power plant during severe accident sequences, including actions taken as part of accident management. The code quantitatively predicts the evolution of a severe accident starting from full power conditions given a set of system faults and initiating events through events such as core melt, reactor vessel failure, and containment failure. Furthermore, models are included in the code to represent the actions that could mitigate the accident by in-vessel cooling, external cooling of the reactor pressure vessel, or cooling the debris in containment. A key element tied to using a code like MAAP4 is an uncertainty analysis. The purpose of this paper is to present a MAAP4 based analysis to examine the sensitivity of a key parameter, in this case hydrogen production, to a set of model parameters that are related to a Level 2 PRA analysis. The Level 2 analysis examines those sequences that result in core melting and subsequent reactor pressure vessel failure and its impact on the containment. This paper identifies individual contributors and MAAP4 model parameters that statistically influence hydrogen production. Hydrogen generation was chosen because of its direct relationship to oxidation. With greater oxidation, more heat is added to the core region and relocation (core slump) should occur faster. This, in theory, would lead to shorter failure times and subsequent "hotter" debris pool on the containment floor.

• 한국산학기술학회논문지
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• 제18권4호
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• pp.216-223
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• 2017

화학물질은 전 세계적으로 1,500만 여종 이상 상업적으로 이용되고 있을 정도로 현대사회의 필수적인 요소이다. 그러나 이러한 화학물질 중에서 국민의 건강과 환경을 위협하는 위험성을 내포하고 있는 유해화학물질이 상당수 존재한다. 과거 사례를 통해 화학사고가 발생하면 인간의 생명에 얼마나 큰 위험성을 내포하고 있는지 알 수 있다. 화학물질사고의 특성상 짧은 시간에 큰 피해로 확산할 수 있으므로, 사전에 예방하고 사고발생 후에는 즉각적이고 신속한 대응이 매우 중요하다. 이에 국내의 화학물질에 대한 법제도가 2015년 기준으로 "유해화학물질관리법"에서 "화학물질의 등록 및 평가 등에 관한 법률"과 "화학물질관리법"의 체계로 이원화되었다. 그러나 현행법상 화학물질종합정보시스템과 화학물질정보처리시스템의 구축 및 운영을 하고 있지만, 여전히 화학사고는 지속적으로 발생하고 있다. 이러한 시스템은 화학물질사고 대응시스템이라기보다는 화학물질 정보에 그 목적을 둔 종합정보시스템이기에, 실질적인 사고대응에는 한계가 존재한다. 본 연구에서는 유해화학물질의 정보관리체계, 대응관리체계 및 화학물질 관리 지원 근거에 대해 분석하고, 이를 통한 현행 화학물질관리법 등의 개정방향과 지자체별 화학물질대응시스템을 개발 운영할 수 있도록 법제도 개선방안을 제안하고자 한다.

• 한국재난정보학회 논문집
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• 제8권2호
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• pp.178-187
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• 2012

화학물질의 사용량 증가에 따라 일반국민이 화학물질 또는 화학제품에 노출되는 사례가 빈번하게 발생하고 있어 응급정보 제공 수요가 급증하고 있으며, 신규 화학물질의 도입에 따라 화학물질 정보의 지속적인 구축 필요성이 제기되고 있다. 이에 따라, 환경부는 국내 유통 중인 화학제품 중심으로 상세물질정보를 지속적으로 확충하여 일반국민에게까지 정보 제공 범위를 확대하는 화학사고 응급대응정보시스템 구축사업을 단계적으로 추진하여 왔다. 이를 통해 24시간 정보제공이 가능하도록 웹 서비스 기반을 마련하여 화학제품 또는 화학물질에 노출된 일반인 또는 현장 대응요원에게 실효성 있는 응급대응정보가 전달될 수 있도록 정보시스템을 구축하여 운영하고 있다.

• 한국가스학회지
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• 제12권2호
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• pp.118-123
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• 2008

도시에는 에너지 시설물로서 고압가스 저장시설 및 고압가스 배관 등 위험물을 취급하는 시설이 산재해 있고, 이런 시설들의 효율적인 위험성 분석 및 관리시스템의 부재로 사고 가능성이 상존하며 선진국에 비해 상대적으로 높은 사고율을 보이고 있다. 에너지 시설물에서 발생하는 사고는 시설 자체의 막대한 피해 뿐만 아니라 시설 주변 지역에 미치는 영향이 매우 크므로, 본 연구에서는 사고영향 분석을 통한 비상대응 시스템을 적용하여 사고피해 정도에 대한 정보를 이용한 체계적인 대응체제를 구축하였다.

• 한국안전학회지
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• 제26권5호
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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.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2650-2659
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• 2022

The dense granular flow spallation target is a new target concept proposed for an Accelerator-Driven Sub-critical (ADS) system. In this paper, the beam-target configurations of a tungsten granular flow target for the ADS with a thermal power of 1 GW is explored. The beam profile options using different scanning methods are discussed. The critical geometry parameters are adjusted to investigate the performance of the granular target from the aspects of neutron efficiency, stability and temperature distribution in target medium. To figure out how the target under accident conditions would behave, different clogging conditions are induced in the simulation. The dynamic processes are analyzed and some important parameters such as abnormal temperature rise and beam cutoff time window are obtained. The response of the sub-critical reactor to a clogging accident is also investigated. It is indicated that the monitoring of the granular flow by the neutron detectors in the sub-critical core will be effective.