• Title/Summary/Keyword: 원자력사고

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Analysis on the Factors Influencing Risk Perception and Risk Taking Behavior to Japanese Fishery Products: Focused on Affect Factor (일본산 수입 수산물에 대한 위험인식, 섭취 행동에 영향을 미치는 요인 분석: 감정요인을 중심으로)

  • Joo, Jungmin;You, Myoung-Soon
    • Journal of Food Hygiene and Safety
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    • v.31 no.3
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    • pp.167-175
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    • 2016
  • After Fukushima Daiichi nuclear disaster, Korean government banned to import of Japanese fishery products that comes from north region of Japan. As 'fishery product trade dispute' between Korea and Japan is still in progress, consumers have been threatened their food safety. This study is to examine the factors influencing consumer's risk perception to Japanese fishery products and risk taking behavior. Survey was conducted with 1,500 adult during sep-oct 2012. The result can represent the role of affect with risk perception of Japanese fishery product. People who have negative affect to Japanese fishery products have higher risk perception. Also negative affection can influence to risk taking behavior. However the degree of fatalism is not significant factor to risk taking behavior.

Implementation of the Traffic Control System based Low Cost Dual Modular Redundancy (저비용 이중화 시스템 기반 교통신호제어 (시스템) 구현)

  • Lee, Dong-Woo;Na, Jong-Whoa;Kim, Nam-Sun
    • Journal of Advanced Navigation Technology
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    • v.21 no.5
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    • pp.491-500
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    • 2017
  • This paper investigates a low cost dual modular redundancy system based on heartbeat which can be applied to traffic control signal system. Failure of the traffic control signal system can cause traffic confusion and traffic accidents. Therefore safety and reliability of traffic control should be secured using fault tolerance technology. To do this, we configured a redundant board using the open source hardware and the heartbeat technique of Linux HA. The function of the traffic signal control system was verified and the fault recovery time was measured using fault injection test. As a result of the test, the fault recovery time was confirmed to be less than 9 seconds on average, confirming that the reliability target time is satisfied. Based on the results of this study, it is expected that it can be applied to fields requiring high reliability systems such as aviation, space, and nuclear power embedded systems.

플라즈마 대면부품 성능 평가를 위한 고열부하시험시설(KoHLT-EB) 구축

  • Kim, Seok-Gwon;Jin, Hyeong-Gon;Sin, Gyu-In;Lee, Eo-Hwak;Yun, Jae-Seong;Lee, Dong-Won;Jo, Seung-Yeon
    • Proceedings of the Korean Vacuum Society Conference
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    • 2014.02a
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    • pp.468-468
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    • 2014
  • 우리나라는 미국, EU, 러시아, 중국, 인도 등 다국간 협력 사업인 국제핵융합실험로(ITER) 사업에 참여하고 있으며, 블랑켓 일차벽 및 시험용 블랑켓 모듈(Test Blanket Module, TBM) 제작기술 개발에 필요한 고열부하 검증시험을 국내에서 자체적으로 실시하기 위한 고열부하시험 시설을 구축하였다. 한국원자력연구원에 설치된 고열부하시험 시설의 주요 사양은 다음과 같다. 열원으로는 전자빔을 사용하며, 빔출력은 최대 300 kW이고, 최대 출력밀도는 $10GW/m^2$이다. 전자빔의 최대 가속전압은 60 kV이고, 최대 조사 면적은 설계상 $70cm{\times}50cm$이다. 고열부하 장비는 핵융합환경과 유사한 고열부하를 시험대상물에 인가하여 접합 및 냉각 성능을 평가하는 장비이며, ITER 블랑켓 및 TBM 일차벽의 경우 약 $0.5MW/m^2$, 가속실험 혹은 사고 시 순간 시나리오 해석을 위해서 $5MW/m^2$까지 고려되기도 한다. ITER 블랑켓 일차벽 제작기술 개발 및 검증(2004~2011)에서는 외국장비(러시아 TSEFEY, 일본 JEBIS, 독일 JUDITH)를 활용하였으나, 고비용 문제와 장비 이용 시간의 제한에 따라 사용이 어려워, 국내에서는 KoHLT-1, 2 장비를 자체 구축하여 활용하여 왔다. 현재는 높은 열부하 인가조건, 약 $5MW/m^2$을 달성하기 위해서 전자빔을 이용한 고열부하시험 장치를 마련하였으며, ITER 블랑켓 일차벽 Semi-Prototype 검증시험, TBM, KSTAR 디버터 실험 등 핵융합로 일차벽 개발에 활용하고 있다. 전자빔, 전원 및 진공 chamber 등 전체 고열부하 시험장치를 구축하여 ITER 장치를 포함해서 토카막 디버터 등 핵융합 플라즈마 대면부품 (Plasma Facing Components, PFC) 재료 개발과 국방, 항공우주 분야의 열유속 게이지 측정법 향상 연구, 로켓 추진 엔진 연소실의 열유속 모니터링 연구, 항공기 프로펠러 연구 등에 활용할 수 있을 것으로 기대된다.

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Public Evacuation Time Estimates within EPZ of Ulchin Site (울진원전 방사선비상계획구역 내의 주민 소개시간 예측)

  • Chung Yang-Geun;Lee Gab-Bock;Bang Sun-Young;Kim Sung-Min;Lee Eun-Mi
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.3 no.4
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    • pp.359-372
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    • 2005
  • The strong protection method of radiation emergency preparedness is the evacuation when a great deal of radionuclide material is released to environment. Required factors for evacuation time estimate of Ulchin nuclear power plant site were investigated. The traffic capacity and the traffic volume by season were investigated for the traffic analysis and simulation within EPZ of Ulchin site. As a result, the background traffic volume by season were established. The NETSIM code was applied to simulate for 12 scenarios in the event of normal traffic/summer peak traffic/winter peak traffic, daytime/night, and normal weather/adverse weather conditions. The results showed that the evacuation time required for total vehicles to move out from EPZ took generally $210\~315$ minutes. The evacuation time took longer about 45 minutes at night than in the daytime, and 45 minutes in adverse weather than normal condition.

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Cable Functional Failure Time Evaluation for a Main Control Room Fire using Fire Dynamic Simulator (FDS 이용한 주제어실 화재시 케이블 기능상실시간 평가)

  • Lim, Heok-Soon;Kim, In-Hwan;Kim, Myung-Su
    • Fire Science and Engineering
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    • v.30 no.3
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    • pp.79-85
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    • 2016
  • Serious electrical problems, such as shorts, ground faults, or circuits, often cause fire events in the fire proof zone of nuclear power plants. These would be directed to the loss of safe shutdown capabilities performed by safety-related systems and equipment. The fire event can be treated with the basic design principle that safety systems should maintain their functions with redundancy and independency. In the case of a cable fire in the main control room, operators cannot perform their mission properly and can misjudge the situation because of spurious operation, incorrect indication or instrument. These would deteriorate the plant capabilities of safety shutdown and result in disastrous conditions. Therefore, during a main control room fire, 5 minutes of operator action time is very important to operate the safety shutdown components. This paper describes the cable functional failure temperature criteria and conducted a cable functional failure time evaluation using Fire Dynamic Simulator to obtain the operator action time for a main control room fire.

A Study on the Design of CBRN Response Training Program in Korea Using Activity-Action Diagram Method (Activity-Action Diagram 기법을 활용한 한국형 화생방 교육훈련 프로그램 설계에 관한 연구)

  • Ham, Eun-Gu;Kim, Tae-Hwan
    • Journal of the Society of Disaster Information
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    • v.10 no.1
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    • pp.159-169
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    • 2014
  • The development of science and technology to accompany the convenience of civilization but in addition to nuclear, gas, explosion, accident and spill all over the world with the possibility of a chemical or biological terrorism response efforts collectively as a response to the urgent task of a nation. In this study major economies such as the U.S. and Canada analyzed to investigate the CBRN training programs to fit the reality in Korea CBRN training programs were developed. also the development of training programs to CBRN Korean Activity-Action Diagram technique utilized by CBRN scenarios corresponding to each event needs to be taken when the Activity is defined by its detailed definition of corrective actions for the CBRN Activity to define context-sensitive actions in particular to enable the functionality of the structure in case of CBRN emergency initial response was to establish education and training programs.

Radioactivity Analysis for Reliability Assessment in the Environmental Samples (환경 시료 중 신뢰도 검증을 위한 방사능 분석)

  • Kang, Tae-Woo;Hong, Kyung-Ae
    • Korean Journal of Environmental Agriculture
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    • v.26 no.2
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    • pp.186-191
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    • 2007
  • The objective of this research was to assess the reliability of data and to improve nuclear analytical techniques concerning the Domestic Radioactivity Intercomparison program for environmental radioactivity monitoring of Jeju from 1998 to 2006. Gross beta for filter papers and water samples was determined, and gamma nuclides for natural and artificial nuclides in soil and water samples were analyzed. The gross beta activity of all samples except for the water samples of 1998 and 1999 showed a good agreement within the confidence intervals. In gamma nuclides, $^{40}K$ and $^{137}Cs$ of soil samples and most nuclides in the water samples, with the exception of several nuclides, were evaluated to be reliable. Based on these results, it is considered that a reliable method for the analysis and monitoring of environmental radioactivity were established, which may play an important role in case of emergency radiation accident.

Incorporation of Droplet Breakup Model at Spacer Grid into RELAP5/ MOD2 (핵 연료봉 지지격자에 의한 Droplet Breakup Model의 RELAP5 / MOD2 삽입)

  • Park, Jong-Ho;Lee, Sang-Yong;Kim, Si-Hwan;Chang, Soon-Heung
    • Nuclear Engineering and Technology
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    • v.22 no.4
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    • pp.326-336
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    • 1990
  • Recent experiments show the existence of spacer grid improves the heat removal from the fuel rods during the reflood phase of LOCA. The local heat transfer within and downstream of the grid is increased due to the earlier quenching than rod surface, shattering of the entrained droplets into smaller ones which can be more easily evaporated and enhanced turbulent effect. Therefore, the consideration of these phenomena is necessary for the DFFB regime which prevails above the water level during the reflood. In this paper, droplet breakup model at spacer grid has been developed and incorporated into RELAP5/MOD2. Verification calculations are carried out for FEBA tests which examine the thermalhydraulic performance of grid spacer during reflood.

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An Assessment of the Best Estimate Thermal-Hydraulic Analysis Code CATHARE on CREARE Downcomer Experiment (CREARE Downcomer실험에 대한 최적열수력 분석용 전산코드 CATHARE의 검증)

  • Chang, Won-Pyo;Lee, Jae-Hoon;Kim, Dong-Su;Chae, Sung-Ki
    • Nuclear Engineering and Technology
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    • v.24 no.3
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    • pp.274-284
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    • 1992
  • A 1/15-scale CREARE experiment, which simulates the thermal-hydraulic behavior in the reactor pressure vessel of a PWR during a hypothetical Loss Of Coolant Accident, has been analyzed using CATHARE code for the associated model assessment to represent the phenomenon. The key parameters examined in the CREARE experiment were known as ECC water injection rate. ECC water subcooling, system pressure, and steam flow rate coming out from the core bottom. The present CATHARE simulation, however, has been mainly focused on qualitative analysis of a countercurrent flow in the downcomer. The discrepancy of the simulation results with the experimental data is considered arising primarily from an inadequate numerical representation as well as an interfacial friction model. Accordingly it is suggested from the sensitivity studies that either multidimensional approach or further examination of momentum equations at a junction near a volume element in CATHARE be necessary in order to represent the phenomenon more realistically.

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Influence of Radioactive Contamination to Agricultural Products Due to Dry and Wet Deposition Processes During a Nuclear Emergency (원자력 사고 중 핵종의 건. 습침적에 따른 농작물 오염 영향)

  • Hwang, Won-Tae;Kim, Eun-Han;Suh, Kyung-Suk;Han, Moon-Hee;Choi, Pong-Ho;Lee, Chang-Woo
    • Journal of Radiation Protection and Research
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    • v.27 no.3
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    • pp.165-170
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    • 2002
  • Combined with deposition model onto the ground of radionuclides, the influence of radioactive contamination to agricultural products was analyzed due to wet deposition as well as dry deposition from radioactive air concentration during a nuclear emergency. The previous dynamic food chain model, in which initial input parameter is only radionuclide concentrations on the ground, was improved for the evaluating of radioactive contamination to agricultural products from either radionuclide concentrations in air or radionuclide concentrations on the ground. As the results, in case of deposition onto the ground, wet deposition was more dominant process than thy deposition. While the contamination levels of agricultural products were dependent on the a variety of factors such as radionuclides and rainfall rate. It means that the contamination levels of agricultural products are determined from which is more dominant process between deposition on the ground and interception onto agricultural plants.