• 제목/요약/키워드: radiation accident

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Panel Session toward Improved Communication and Engagement with the Public after the Fukushima Daiichi Nuclear Power Plant Accident: Study Reports and Discussion with Specialists from Relevant Fields

  • Yoshida, Hiroko;Kuroda, Yujiro;Kono, Takahiko;Naito, Wataru;Sakoda, Akihiro
    • Journal of Radiation Protection and Research
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    • 제46권3호
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    • pp.134-142
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    • 2021
  • Background: From 2018 to 2020, the Expert Study on Public Understanding after the Fukushima Daiichi Nuclear Power Plant Accident (the Expert Study Group) identified and analyzed activities designed to promote public understanding of science and radiation since the Fukushima accident, and held discussions on how to achieve public understanding in the situation where public confidence has been lost, and how experts should prepare for dealing with the public. This panel session was held at the 53rd meeting of the Japan Health Physics Society on June 30, 2020. Materials and Methods: First, three subgroup (SG) leaders reported their research methods and results. Then, two designated speakers, who participated as observers of the Expert Study Group, commented on the activities. Next, the five speakers held a panel discussion. Finally, the rapporteur summarized. Results and Discussion: SG leaders presented reports from researchers and practitioners in health physics and environmental risks who provided information after the Fukushima accident. During the discussion, experts in sociology and ethics discussed the issues, focusing on the overall goals of the three groups, local (personal) and mass communication, and ethical values. Many of the activities instituted by the experts after the accident were aimed at public understanding of science (that is, to provide knowledge to residents), but by taking into account interactions with residents and their ethical norms, the experts shifted to supporting the residents' decision-making through public engagement. The need to consider both content and channels is well known in the field of health communication, and overlaps with the above discussion. Conclusion: How to implement and promote the public engagement in society was discussed in both the floor and designated discussions. Cooperation between local communities and organizations that have already gained trust is also necessary in order to develop relationships with local residents in normal times, to establish an information transmission system, and to make it work effectively.

대학생들의 방사선에 대한 인식도 (University Students' Awareness of Radiation)

  • 김창규
    • 한국융합학회논문지
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    • 제3권1호
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    • pp.27-34
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    • 2012
  • 2011년 3월 11일 발생한 일본 후쿠시마 원전 사고 후 한국 대학생들의 방사선과 의료 방사선에 대한 생각을 파악하여 방사선에 대한 적절한 교육 방법과 국민들의 방사선 안전에 대한 올바른 대중 커뮤니케이션에 대해 모색하고자 전국 5개도(경기, 강원, 충청, 전라, 경상도)의 4년제 방사선학과가 설치된 대학교에서 790부 설문지를 수거한 후 분석하였다. 설문은 36문항으로 구성하였으며, '방사선이 위험하다'고 느끼는 중요 원인 중 하나는 '적은양의 방사선을 쪼여도 나중에 문제가 생길 수 있다'. ($3.28{\pm}1.05$)로 분석됐다. 방사선에 대한 관리에서는 개인보다는 정부가 나서야 된다는 응답자가 $3.87{\pm}0.89$으로 나타났다. '후쿠시마 원전 사고는 원자력 발전을 하지 말아야 한다는 쪽으로 나의 생각을 바꾸게 했다'라는 문항에는 $2.79{\pm}0.95$로 나타났다. '후쿠시마 원전사고 이후 의료 방사선에 대한 생각이 부정적으로 바뀌었다'라는 문항에는 전체적으로 $2.64{\pm}1.02$, 방사선학과 $2.31{\pm}1.00$, 치위생학과 $2.94{\pm}0.95$, 기타학과 $3.13{\pm}0.82$로 방사선과 관련된 교과목을 수강 경험이 없는 기타학과 학생일수록 부정적인 생각을 가지고 있는 것으로 나타났다. 또한 방사선에 관한 교육이 필요하다고 생각하는 사람이 82.28%로 나타났으며, 그 중 T.V나 인터넷이 가장 효율적인 교육 방법으로 나타났다.

방사능 수치 오염 지도 작성을 위한 방사선 계측 시스템 연구 (Study of Radiation Mapping System for Water Contamination in Water System)

  • 나원경;김한수;연제원;이레나;하장호
    • 방사선산업학회지
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    • 제5권2호
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    • pp.185-189
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    • 2011
  • As nuclear industry has been developed, a various types of radiological contamination has occurred. After 9.11 terror in U.S.A., it has been concerned that terrorists' active area has been enlarged to use nuclear or radioactive substance. Recently, the most powerful earth-quake stroke, which triggered a massive tsunami in Japan and then Fukushima nuclear power plant reactor has suffered from a serious accident in history. The Fukushima reactor accident has occurred an anxiety of radiation leaks and about 170,000 people have been evacuated from the accidental area near the nuclear power plant. For these reasons, a social chaos can be occurred if radiological contamination occurs to the supply system for the drinking water. As such, the establishment of the radiation monitoring system for the city main water system is compelling for the national security. In this study, a feasibility test of radiation monitoring system which consists of unified hybrid-type radiation detectors was experimented for multi detection system by using gamma-ray imaging. The hybrid-type radiation sensors were fabricated with CsI(Tl) scintillators and photodiodes. A preamplifier and amplifier was also fabricated and assembled with the sensor in the shielding case. For the preliminary test of detection of radiological contamination in the river, multi CsI(Tl)-PIN photodiode radiation detectors and $^{137}Cs$ gamma-ray source were used. The DAQ was done by Linux based ROOT program and NI DAQ system with Labview program. The simulated contamination was assumed to be occurred at Gapcheon river in Daejeon city. Multi CsI(Tl)-PIN photodiode radiation detectors were positioned at the Gapcheon river side. Assuming that the radiological contaminations flows in the river the $^{137}Cs$ gamma-ray source has been moved and then, the contamination region was reconstructed.

3차원 방사선 탐지장치용 검출센서의 차폐체 및 Collimator 구조 분석 연구 (The Analysis of the Collimator & Radiation Shield for the Radiation Sensor for the 3Dimension Radiation Detection)

  • 황영관;이남호;박성훈;정상훈;김종열;최명진
    • 한국정보통신학회:학술대회논문집
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    • 한국정보통신학회 2014년도 춘계학술대회
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    • pp.707-709
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    • 2014
  • 핵폭발이나 원자력 발전시설 사고와 같이 대규모 방사선사고 발생 시 주변지역은 감응방사선 또는 방사선 낙진으로 인해 오염된다. 이러한 오염지역을 원격에서 탐지하여 오염물질에 대한 분포 및 오염 정도를 확보한다면 오염물질 제거뿐만 아니라 오염에 대한 피해를 최소화 할 수 있다. 본 논문에서는 오염 물질을 탐지하기 위한 스테레오 검출기 개발의 일환으로 MCNP코드를 이용하여 검출기의 차폐체 및 콜리메이터를 설계하고 교정된 감마선 조사시설을 통해 일정한 선량의 감마선을 조사하여 차폐체 및 콜리메이터에 대한 영향을 분석하였다. 본 논문의 결과는 방사선 탐지를 위한 효율적인 검출기 구조를 설계를 위한 기초자료로 활용될 것이다.

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P-mSHEL 요인분석 모델을 이용한 방사선종양학과 방사선 안전사고 위험 요인 평가 (Assessment of Radiation Safety Incident Risk Factors in Radiation Oncology Department Using the P-mSHEL Factor Analysis Model)

  • 김영록;김대건;정재홍
    • 대한방사선기술학회지:방사선기술과학
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    • 제47권4호
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    • pp.287-294
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    • 2024
  • Radiation oncology departments are at high risk for potential radiation safety incidents. This study aimed to identify risk factors for these incidents using the P-mSHEL (Patient, Management, Software, Hardware, Environment, and Liveware) model and to evaluate potential accident types through Failure Mode and Effects Analysis (FMEA). FMEA identified seven accident types with high Risk Priority Number (RPN). A total of 56 detailed risk factors were classified using the P-mSHEL model, and measures to prevent radiation safety incidents were implemented. The effect of these preventive measures on workers' safety perception was confirmed through two indicators (FMEA and safety perception). After implementing the preventive measures, the FMEA analysis showed that the highest reduction in RPN was for A-6 (radiation exposure while other patients/guardians are present) with a reduction rate of 33.3%, followed by B-3 (radiation exposure while staff are present) with a reduction rate of 33.3%. Overall safety perception significantly improved after the preventive measures (4.17±0.35) compared to before (2.76±0.33) (p<0.05), with notable increases in both employee safety culture (3.93±0.51) and patient safety culture (3.73±0.62) (p<0.05). This study identified risk factors in radiation oncology departments. Continuous management, maintenance, and fostering a strong safety culture are crucial for preventing incidents. Regular problem identification and collaboration with relevant departments are essential for maintaining safety standards.

Multi-objective path planning for mobile robot in nuclear accident environment based on improved ant colony optimization with modified A*

  • De Zhang;Run Luo;Ye-bo Yin;Shu-liang Zou
    • Nuclear Engineering and Technology
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    • 제55권5호
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    • pp.1838-1854
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    • 2023
  • This paper presents a hybrid algorithm to solve the multi-objective path planning (MOPP) problem for mobile robots in a static nuclear accident environment. The proposed algorithm mimics a real nuclear accident site by modeling the environment with a two-layer cost grid map based on geometric modeling and Monte Carlo calculations. The proposed algorithm consists of two steps. The first step optimizes a path by the hybridization of improved ant colony optimization algorithm-modified A* (IACO-A*) that minimizes path length, cumulative radiation dose and energy consumption. The second module is the high radiation dose rate avoidance strategy integrated with the IACO-A* algorithm, which will work when the mobile robots sense the lethal radiation dose rate, avoiding radioactive sources with high dose levels. Simulations have been performed under environments of different complexity to evaluate the efficiency of the proposed algorithm, and the results show that IACO-A* has better path quality than ACO and IACO. In addition, a study comparing the proposed IACO-A* algorithm and recent path planning (PP) methods in three scenarios has been performed. The simulation results show that the proposed IACO-A* IACO-A* algorithm is obviously superior in terms of stability and minimization the total cost of MOPP.

수소 Tube Trailer 저장시설에서의 수소가스 누출에 따른 사고피해예측에 관한 연구 (A Study of Damage Assessment Caused by Hydrogen Gas Leak in Tube Trailer Storage Facilities)

  • 김종락;황성민;윤명오
    • 한국화재소방학회논문지
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    • 제25권6호
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    • pp.32-38
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    • 2011
  • 산업현장에서 폭발성가스의 사용이 꾸준이 증가 함에 따라 작업자는 물론 일반지역주민들에까지 사고로 인한 생명에 위험을 처하기도 한다. 수소사용공정에서의 사고피해는 공정자체에 국한 되는 것이 아니라 대형화재나 폭발로 이어져 다수의 사상자를 유발시키므로 사고의 유형과 원인을 규명하고 피해규모를 예측하여 이에 대한 안전대책을 수립, 운영하는 것이 필요하다. 본 연구에서는 MLCC(Multi Layer Ceramic Capacitor) 소성공정의 수소저장 사용시설에서 화재 폭발시 위험범위를 예측하였다. 실제 사고데이터의 분석결과 사고발생빈도가 가장 많은 배관누출에 대하여 사고 피해예측 시나리오 모델로 선정, 적용하였다. 10 mm Hole에서 120 Bar의 압력으로 수소가스 누출시 Jet fire가 발생되며 Radiation Level 4($kw/m^2$)의 경우 최대 12.45 m까지 복사열의 영향을 주었다. 또한 사고피해 예측을 통한 안전성확보와 개선방안을 제시하였다.

극저준위 콘크리트, 금속 해체방폐물의 방사선적 특성을 고려한 매립형 처분시설 방사선작업자 예비 피폭선량 평가 (Preliminary Radiation Exposure Dose Evaluation for Workers of the Landfill Disposal Facility Considering the Radiological Characteristics of Very Low Level Concrete and Metal Decommissioning Wastes)

  • 도호석;조예슬;강현구;하재철
    • 방사선산업학회지
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    • 제17권4호
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    • pp.509-518
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    • 2023
  • The Kori Unit 1 nuclear power plant, which is planned to be dismantled after permanent shutdown, is expected to generate a large amount of various types of radioactive waste during the dismantling process. For the disposal of Very-low-level waste, which is expected to account for the largest amount of generation, the Korea Radioactive waste Agency (KORAD) is in the process of detailed design to build a 3-phase landfill disposal facility in Gyeongju. In addition, a large container is being developed to efficiently dispose of metal and concrete waste, which are mainly generated as Very low-level waste of decommissioning. In this study, based on the design characteristics of the 3-phase landfill disposal facility and the large container under development, radiation exposure dose evaluation was performed considering the normal and accident scenarios of radiation workers during operation. The direct exposure dose evaluation of workers during normal operation was performed using the MCNP computer program, and the internal and external exposure dose evaluation due to damage to the decommissioning waste package during a drop accident was performed based on the evaluation method of ICRP. For the assumed scenario, the exposure dose of worker was calculated to determine whether the exposure dose standards in the domestic nuclear safety act were satisfied. As a result of the evaluation, it was confirmed that the result was quite low, and the result that satisfied the standard limit was confirmed, and the radiational disposal suitability for the 3-phase landfill disposal facility of the large container for dismantled radioactive waste, which is currently under development, was confirmed.

사용후핵연료 습식저장시설 사고 안전성 평가 연구 현황 및 사고 사례 분석 (Analysis on Study Cases of Safety Assessment and Cases for Spent Nuclear Fuel Pool Accident)

  • 이신동;김혁재;손건우;김광표
    • 방사선산업학회지
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    • 제17권3호
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    • pp.283-292
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    • 2023
  • Spent nuclear fuel corresponds to high-level radioactive waste that has high decay heat and radioactivity. Accordingly, Spent nuclear fuel withdrawn from the reactor core is primarily stored and managed in a spent nuclear fuel pool in the nuclear power plant to reduce decay heat and radioactivity. In Korea, most nuclear power plant store all spent nuclear fuel in a spent nuclear fuel pool. For wet storage, there are no defense in depth different with reactor core. The study related to spent nuclear fuel pool accident should be carried out to ensure safety. Therefore, it is necessary to analyze previous study cases related to safety of spent nuclear fuel pool and accident cases to build foundational knowledge. The Objective of this study is to analyze study cases of safety assessment and cases for spent nuclear fuel pool accident. For analyzing study cases of safety assessment, possible phenomena when spent nuclear fuel pool accident occurring identified, Subsequently, study cases for safety assessment about each phenomena were investigated, and materials & methods and results for each study are analyzed. For analyzing cases for spent nuclear fuel pool accident, we analyzed accident cases caused by loss of cooling and loss of coolant in spent nuclear fuel pool. Subsequently, causes and change of water level and temperature by each accident case are analyzed. As a result of the analysis on study cases of spent nuclear fuel pool accident, the results of the study conducted by each research institute were vary depending on the computer code, materials & methods of experiment and major assumptions used in the study. As a result of analyzing cases for spent nuclear fuel pool accident, it was found that accident cases for loss of cooling is more than cases for loss of coolant accident. Even though the types of accident in spent nuclear fuel pool were similar, the specific causes were different by each accident case. All the accident cases analyzed did not lead to severe accidents, such as nuclear fuel being exposed to the air. The result of this study will be used as fundamental data for study on spent nuclear fuel pool accident that will be conducted in the future.