• 제목/요약/키워드: Fukushima Nuclear Accident

검색결과 225건 처리시간 0.052초

국가안보측면으로서의 인공강우기술 고찰 (Study on Consideration of Artificial Rain Technology in Aspect of National Security)

  • 최기남;이선제
    • 융합보안논문지
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    • 제12권2호
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    • pp.99-106
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    • 2012
  • 2010년 3월 11일 대한민국 동해를 건너 위치한 일본에서 강진과 해일로 인하여 후쿠시마원전이 중단되고 폭발하여 방사능물질이 누출되었다. 한 국가에서 발생한 사고지만 누출된 방사능 물질은 해류와 기류를 타고 전 세계에 확산되었다. 국내에도 사고 이후 방사능비가 내린다는 공포심에 혼란이 있었고, 사고 발생 1년이 지나도 방사능오염에 대한 문제는 해결되지 않고 있다. 즉 이웃나라의 원전사고는 국내에도 큰 위협이 되는데 일본 뿐 만 아니라 서해 건너 중국해변에도 원자력발전소가 위치하고 있다. 이웃나라의 원전사고 위협이외 군사적 대치를 하고 있는 북한은 세계3위의 생화학무기 보유국이며 2010년 11월에는 연평도 포격도발을 하는 등 언제든 남한에 생화학물질을 살포 할 수 있는 상황이다. 본 연구는 이러한 위협에 대응하는 전략으로 기상조절기술인 인공강우기술을 접목해 보았다. 원전사고시 방사능물질과 북한의 생화학무기는 기상조건에 따라 농도가 달라 질 수 있으므로 인공강우기술만으로 완벽하게 위협을 제거할 수 없지만, 심리적 측면과 피해저감을 위한 방법으로 시도해 볼 가치가 있다. 국민안전확보를 위한 국가의 안보측면으로서 인공강우기술을 사용하기 위해서는 ADD와 같은 연구기관에서 상시적이고 적극적으로 기술연구개발을 해야 할 것이다.

방사능 오염식품과 방사선조사 식품에 관한 유치원 부모의 인식 - 2011년 일본 원전사고의 영향력을 중심으로 - (Kindergarten parents' perceptions on radioactive-contaminated foods and irradiated foods - Focus on the accident of unclear plant in Japan, 2011 -)

  • 양진희;박윤;여화연
    • 한국방사선학회논문지
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    • 제6권6호
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    • pp.435-440
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    • 2012
  • 본 연구는 2011년 일본 후쿠시마 원자력 발전소 방사선 누출사고가 방사능 오염식품과 방사선 조사식품에 관한 유치원 부모의 인식에 미치는 영향을 분석하여 국민건강자료를 제공하는데 의의가 있다. 본 연구는 2012년 8월 J시의 K와 M유치원의 학부모 205명을 대상으로 설문지를 배부하여 회수된 178명의 자료를 분석하였다. 본 연구의 결과, 일본 원전사고는 방사능 오염식품에 대한 학부모의 불안감에 영향을 미쳤으며, 방사선조사 식품에 대한 부모들의 인식은 낮았다. 결론적으로 방사선조사 식품에 대한 유치원 부모들의 인식을 높이고, 방사능 오염식품과의 명확한 구분 및 올바른 인식을 돕는 적극적인 홍보와 부모교육이 이루어져야 할 것이다.

Large Scale Experiments Simulating Hydrogen Distribution in a Spent Fuel Pool Building During a Hypothetical Fuel Uncovery Accident Scenario

  • Mignot, Guillaume;Paranjape, Sidharth;Paladino, Domenico;Jaeckel, Bernd;Rydl, Adolf
    • Nuclear Engineering and Technology
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    • 제48권4호
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    • pp.881-892
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    • 2016
  • Following the Fukushima accident and its extended station blackout, attention was brought to the importance of the spent fuel pools' (SFPs) behavior in case of a prolonged loss of the cooling system. Since then, many analytical works have been performed to estimate the timing of hypothetical fuel uncovery for various SFP types. Experimentally, however, little was done to investigate issues related to the formation of a flammable gas mixture, distribution, and stratification in the SFP building itself and to some extent assess the capability for the code to correctly predict it. This paper presents the main outcomes of the Experiments on Spent Fuel Pool (ESFP) project carried out under the auspices of Swissnuclear (Framework 2012-2013) in the PANDA facility at the Paul Scherrer Institut in Switzerland. It consists of an experimental investigation focused on hydrogen concentration build-up into a SFP building during a predefined scaled scenario for different venting positions. Tests follow a two-phase scenario. Initially steam is released to mimic the boiling of the pool followed by a helium/steam mixture release to simulate the deterioration of the oxidizing spent fuel. Results shows that while the SFP building would mainly be inerted by the presence of a high concentration of steam, the volume located below the level of the pool in adjacent rooms would maintain a high air content. The interface of the two-gas mixture presents the highest risk of flammability. Additionally, it was observed that the gas mixture could become stagnant leading locally to high hydrogen concentration while steam condenses. Overall, the experiments provide relevant information for the potentially hazardous gas distribution formed in the SFP building and hints on accident management and on eventual retrofitting measures to be implemented in the SFP building.

HAZARD ANALYSIS OF TYPHOON-RELATED EXTERNAL EVENTS USING EXTREME VALUE THEORY

  • KIM, YOCHAN;JANG, SEUNG-CHEOL;LIM, TAE-JIN
    • Nuclear Engineering and Technology
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    • 제47권1호
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    • pp.59-65
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    • 2015
  • Background: After the Fukushima accident, the importance of hazard analysis for extreme external events was raised. Methods: To analyze typhoon-induced hazards, which are one of the significant disasters of East Asian countries, a statistical analysis using the extreme value theory, which is a method for estimating the annual exceedance frequency of a rare event, was conducted for an estimation of the occurrence intervals or hazard levels. For the four meteorological variables, maximum wind speed, instantaneous wind speed, hourly precipitation, and daily precipitation, the parameters of the predictive extreme value theory models were estimated. Results: The 100-year return levels for each variable were predicted using the developed models and compared with previously reported values. It was also found that there exist significant long-term climate changes of wind speed and precipitation. Conclusion: A fragility analysis should be conducted to ensure the safety levels of a nuclear power plant for high levels of wind speed and precipitation, which exceed the results of a previous analysis.

한수원 안전문화 원칙 및 평가 유효성 검증 (Effectiveness Verification of KHNP Safety Culture Principles and Assessment)

  • 허남용;김영갑;송태영
    • 한국압력기기공학회 논문집
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    • 제10권1호
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    • pp.25-30
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    • 2014
  • Korea Hydro & Nuclear Power Co.,LTD(KHNP) was strongly interested in promotion of employee's Safety Culture because it is needed to change the recognition of Safety Culture after the Fukushima accident and Kori-1 blackout event. So, KHNP developed the KHNP Safety Culture Definition, Principles and Attributes and shared them with all employees. By using them, Safety Culture Assessment for a site plant employees was carried out. Through the pilot Safety Culture Assessment in 2012, In 2013, it was expanded to 6 plants and various improvements had been obtained from that. KHNP has been developing a variety of training materials, Safety Culture posters, videos which was designed to give lessons about safety culture with a variety of event cases. And keep trying to form Safety Culture Circumstances In this study, statistic methods are used to verify the effectiveness of KHNP Safety Culture Principles and Safety Culture Assessment.

해양환경 모니터링 센서 시스템 개발에 관한 연구 (Study on Development of Marine Environment Monitoring Sensor System)

  • 윤영
    • 한국항해항만학회:학술대회논문집
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    • 한국항해항만학회 2019년도 추계학술대회
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    • pp.211-212
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    • 2019
  • 후쿠시마 원전사고 이후, 오염수 방출등에 의한 해양오염문제가 크게 대두되고 있다. 본 논문은 해양환경 모니터링 센서 시스템 개발에 관한 연구에 관한 내용이다. 본 논문에서는 해양환경 모니터링을 위해서 실시간의 해상에서의 여러 가지 해양 오염원을 계측하고 이를 실시간으로 분석하여 관측센터로 전송하는 센서 및 통신 시스템에 관한 연구를 발표하고자 한다.

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Thickness measurements of a Cr coating deposited on Zr-Nb alloy plates using an ECT pancake sensor

  • Jeong Won Park;Bonggyu Ji;Daegyun Ko;Hun Jang;Wonjae Choi
    • Nuclear Engineering and Technology
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    • 제55권9호
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    • pp.3260-3267
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    • 2023
  • Zr-Nb alloy have been widely used as fuel rods in nuclear power plants. However, from the Fukushima nuclear accident, the weakness of the rod was revealed under harsh conditions, and research on the safety of these types of rods was conducted after the disaster. The method of depositing chromium onto the existing Zr-Nb alloy fuel rods is being considered as a means by which to compensate for the weakness of Zr-Nb alloy rods because chromium is strong against oxidation at high temperatures and has high strength. In order to secure these advantages, it is important to maintain the Cr thickness of the rods and properly inspect the rods before and during their use in power generation. Eddy current testing is a typical means of evaluating the thickness of thin metals and detecting surface defects. Depending on the size and shape of the inspected object, various eddy current sensors can be applied. In particular, because pancake sensors can be manufactured in very small sizes, they can be used for inspections even in narrow spaces, such as a nuclear fuel assembly. In this study, an eddy current technique was developed to confirm the feasibility of Cr coating thickness evaluations. After determining the design parameters of the pancake sensor by means of a FEM simulation, a FPCB pancake sensor was manufactured and the optimal frequency was selected by measuring minute changes in the Cr-coating thickness using the developed sensor.

Efficient design of a ∅2×2 inch NaI(Tl) scintillation detector coupled with a SiPM in an aquatic environment

  • Kim, Junhyeok;Park, Kyeongjin;Hwang, Jisung;Kim, Hojik;Kim, Jinhwan;Kim, Hyunduk;Jung, Sung-Hee;Kim, Youngsug;Cho, Gyuseong
    • Nuclear Engineering and Technology
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    • 제51권4호
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    • pp.1091-1097
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    • 2019
  • After the Fukushima accident in 2011, there has been increased public concern about radioactive contamination of water resources through fallout in neighboring countries. However, there is still no available initial response system that can promptly detect radionuclides. The purpose of this research is to develop the most efficient gamma spectrometer to monitor radionuclides in an aquatic environment. We chose a thallium-doped sodium iodide (NaI(Tl)) scintillator readout with a silicon photo multiplier (SiPM) due to its compactness and low operating voltage. Three types of a scintillation detector were tested. One was composed of a scintillator and a photomultiplier tube (PMT) as a reference; another system consisted of a scintillator and an array of SiPMs with a light guide; and the other was a scintillator directly coupled with an array of SiPMs. Among the SiPM-based detectors, the direct coupling system showed the best energy resolution at all energy peaks. It achieved 9.76% energy resolution for a 662 keV gamma ray. Through additional experiments and a simulation, we proved that the light guide degraded energy resolution with increasing statistical uncertainty. The results indicated that the SiPM-based scintillation detector with no light guide is the most efficient design for monitoring radionuclides in an aquatic environment.

APR+ 확률론적 안전성평가 및 대형냉각재상실사고 성공기준과 파단크기 민감도 분석 (A Study on the Probabilistic Safety Assessment and Sensitivity Analysis of Success Criteria of Large LOCA for APR+)

  • 문호림;김한곤
    • 한국안전학회지
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    • 제31권6호
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    • pp.129-134
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    • 2016
  • Standard design of APR+(advanced power reactor plus) was certified at 2014 by Korea regulatory body. Based on the experience gained from OPR1000 and APR1400, the APR1400 was being developed as a 1,500MWe class reactor using Korean technologies for design code, reactor coolant pump, and man-machine interface system. APR+ has been basically designed to have the seismic design basis of safe shutdown earthquake (SSE) 0.3g, a 4-train safety concept based on N+2 design philosophy, and a passive auxiliary feedwater system (PAFS). Also, safety issues on the Fukushima-type accidents have been extensively reviewed and applied to enhance APR+ safety. APR+ provides higher reliability and safety against tsunami and earthquake. The purpose of this paper is to implement probabilistic safety assessment considering these design features and to analyze sensitivity of core damage frequency for large loss of coolant accident of APR+.

가공제품에 대한 생활주변방사선 실태조사 자료를 활용한 통계분석 (Statistical Analysis Using Living Radiation Survey Data on Processed Products)

  • 최경호;조정근
    • 대한방사선기술학회지:방사선기술과학
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    • 제43권2호
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    • pp.123-128
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    • 2020
  • Radiation Following the 2011 Fukushima nuclear accident in Japan, public interest and anxiety about radiation safety increased, and vague anxiety about commonly exposed living radiation was generated. The Atomic Energy Safety Commission has been conducting a survey of processed products that advertise "negative ions" and "far-infrared" emissions under the Living Radiation Safety Management Act. In this study, in-depth analysis was performed from a statistical point of view using the measurement data presented in the Nuclear Safety Committee's actual survey analysis report as secondary data. As a result, there was a statistically significant difference (p<0.005) between latex and civil affairs products. There were also statistically significant differences (p<0.05) in the results of testing whether there were significant differences in the annual exposure dose between groups after categorizing 71 civil products, including radon beds, into bed, bedding, and living and other categories. The correlation analysis results also confirm that, as is commonly known, the annual doses received from processed products are associated with radon derived from U-238 and Th-232.