• 제목/요약/키워드: Fukushima nuclear accident

검색결과 227건 처리시간 0.031초

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.

프러시안 블루(PB)의 방사성 세슘 흡착 메커니즘 연구 (Adsorption Mechanism of Radioactive Cesium by Prussian Blue)

  • 장성찬;김준영;허윤석;노창현
    • 방사선산업학회지
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    • 제9권3호
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    • pp.127-130
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    • 2015
  • Since the accident at the Fukushima Daiichi power plant, Prussian blue (PB) has attracted increasing attention as a material for use in decontaminating the environment. We have focused the fundamental mechanism of specific $Cs^+$ adsorption into PB in order to develop high-performance PB-based $Cs^+$ adsorbents. The ability of PB to adsorb Cs varies considerably according to its origin such as what synthesis method was used, and under what conditions the PB was prepared. It has been commonly accepted that the exclusive abilities of PB to adsorb hydrated $Cs^+$ ions are caused by regular lattice spaces surrounded by cyanido-bridged metals. $Cs^+$ ions are trapped by simple physical adsorption in the regular lattice spaces of PB. $Cs^+$ ions are exclusively trapped by chemical adsorption via the hydrophilic lattice defect sites with proton-exchange from the coordination water. Prussian blue are believed to hold great promise for the clean-up of $^{137}Cs$ contaminated water around nuclear facilities and/or after nuclear accidents.

Conclusions and Suggestions on Low-Dose and Low-Dose Rate Radiation Risk Estimation Methodology

  • Sakai, Kazuo;Yamada, Yutaka;Yoshida, Kazuo;Yoshinaga, Shinji;Sato, Kaoru;Ogata, Hiromitsu;Iwasaki, Toshiyasu;Kudo, Shin'ichi;Asada, Yasuki;Kawaguchi, Isao;Haeno, Hiroshi;Sasaki, Michiya
    • Journal of Radiation Protection and Research
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    • 제46권1호
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    • pp.14-23
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    • 2021
  • Background: For radiological protection and control, the International Commission on Radiological Protection (ICRP) provides the nominal risk coefficients related to radiation exposure, which can be extrapolated using the excess relative risk and excess absolute risk obtained from the Life Span Study of atomic bomb survivors in Hiroshima and Nagasaki with the dose and dose-rate effectiveness factor (DDREF). Materials and Methods: Since it is impossible to directly estimate the radiation risk at doses less than approximately 100 mSv only from epidemiological knowledge and data, support from radiation biology is absolutely imperative, and thus, several national and international bodies have advocated the importance of bridging knowledge between biology and epidemiology. Because of the accident at the Tokyo Electric Power Company (TEPCO)'s Fukushima Daiichi Nuclear Power Station in 2011, the exposure of the public to radiation has become a major concern and it was considered that the estimation of radiation risk should be more realistic to cope with the prevailing radiation exposure situation. Results and Discussion: To discuss the issues from wide aspects related to radiological protection, and to realize bridging knowledge between biology and epidemiology, we have established a research group to develop low-dose and low-dose-rate radiation risk estimation methodology, with the permission of the Japan Health Physics Society. Conclusion: The aim of the research group was to clarify the current situation and issues related to the risk estimation of low-dose and low-dose-rate radiation exposure from the viewpoints of different research fields, such as epidemiology, biology, modeling, and dosimetry, to identify a future strategy and roadmap to elucidate a more realistic estimation of risk against low-dose and low-dose-rate radiation exposure.

Reduction of Outdoor and Indoor Ambient Dose Equivalent after Decontamination in the Fukushima Evacuation Zones

  • Yoshida-Ohuchi, Hiroko;Kanagami, Takashi;Naitoh, Yutaka;Kameyama, Mizuki;Hosoda, Masahiro
    • Journal of Radiation Protection and Research
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    • 제42권1호
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    • pp.42-47
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    • 2017
  • Background: One of the most urgent issues following the accident at the Fukushima Daiichi nuclear power plant (FDNPP) was the remediation of the land, in particular, for residential area contaminated by the radioactive materials discharged. In this study, the effect of decontamination on reduction of ambient dose equivalent outdoors and indoors was evaluated. The latter is essential for residents as most individuals spend a large portion of their time indoors. Materials and Methods: From December 2012 to November 2014, thirty-seven Japanese single-family detached wooden houses were investigated before and after decontamination in evacuation zones. Outdoor and indoor dose measurements (n = 84 and 114, respectively) were collected based on in situ measurements using the NaI (Tl) scintillation surveymeter. Results and Discussion: The outdoor ambient dose equivalents [$H^*(10)_{out}$] ranged from 0.61 to $3.71{\mu}Sv\;h^{-1}$ and from 0.23 to $1.32{\mu}Sv\;h^{-1}$ before and after decontamination, respectively. The indoor ambient dose equivalents [$H^*(10)_{in}$] ranged from 0.29 to $2.53{\mu}Sv\;h^{-1}$ and from 0.16 to $1.22{\mu}Sv\;h^{-1}$ before and after decontamination, respectively. The values of reduction efficiency (RE), defined as the ratio by which the radiation dose has been reduced via decontamination, were evaluated as $0.47{\pm}0.13$, $0.51{\pm}0.13$, and $0.58{\pm}0.08$ ($average{\pm}{\sigma}$) when $H^*(10)_{out}$ < $1.0{\mu}Sv\;h^{-1}$, $1.0{\mu}Sv\;h^{-1}$ < $H^*(10)_{out}$ < $2.0{\mu}Sv\;h^{-1}$, and $2.0{\mu}Sv\;h^{-1}$ < $H^*(10)_{out}$, respectively, indicating the values of RE increased as $H^*(10)_{out}$ increased. It was found that the values of RE were $0.53{\pm}0.12$ outdoors and $0.41{\pm}0.09$ indoors, respectively, indicating RE was larger outdoors than indoors. Conclusion: Indoor dose is essential as most individuals spend a large portion of their time indoors. The difference between outdoors and indoors should be considered carefully in order to estimate residents' exposure dose before their returning home.

후쿠시마 원전 사고 이후 일반인의 방사선학적 안전성 확보를 위한 제염폐기물 임시저장시설 이격거리 평가 (Evaluation of Separation Distance from the Temporary Storage Facility for Decontamination Waste to Ensure Public Radiological Safety after Fukushima Nuclear Power Plant Accident)

  • 김민준;고아라;김광표
    • 방사성폐기물학회지
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    • 제14권3호
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    • pp.201-209
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    • 2016
  • 후쿠시마 원전사고 이후 광역의 방사성 오염부지가 발생되었으며, 이에 대한 제염작업으로 인하여 다량의 제염폐기물이 발생하였다. 일본에서는 이를 보관하기 위하여 각 지역에 임시저장시설이 운영되고 있으며, 이들 시설들은 피난지시해제가 이루어진 지역의 일반인에 대하여 방사선학적 영향을 미칠 것으로 판단된다. 본 연구에서는 임시저장시설 인근에 거주하는 일반인의 방사선학적 안전성 확보를 위하여 임시저장시설 특성에 따른 거리별 공간 방사선량률 및 선량제한치를 만족하는 임시저장시설로부터의 이격거리를 평가하였다. 이를 위해 임시저장시설의 형태 및 크기, 복토 두께 등을 고려하였으며, MCNPX를 이용하여 방사선량률을 평가하였다. 복토에 의한 차폐효과는 두께가 10 cm일 때 68.9%, 30 cm일 때 96.9%, 50 cm 일 때 99.7%로 나타났다. 임시저장시설 형태에 따른 공간 방사선량률은 지상 보관형일 때 가장 높게 나타났으며, 이어서 반지하 보관형, 지하 보관형일 순으로 나타났다. 임시저장시설 크기에 따른 공간 방사선량률은 $5{\times}5{\times}2m$ 시설을 제외한 시설에 대하여 유사하게 나타났다. 이는 임시저장시설 내 적재된 제염폐기물에 의하여 자기차폐가 이루어지기 때문이다. 최종적으로 크기가 $50{\times}50{\times}2m$이고, 복토가 없는 임시저장시설의 경우, 지상 보관형의 평가된 이격거리는 14 m(최소농도), 33 m(최빈농도), 57 m(최대농도)이며, 반지하 보관형의 이격거리는 9 m(최소농도), 24 m(최빈농도), 45 m(최대농도), 지하보관형의 이격거리는 6 m(최소농도), 16 m(최빈농도), 31 m(최대농도)로 나타났다.

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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한국과 일본의 장기 저탄소 에너지 시나리오에 대한 메타 리뷰

  • 박년배
    • 자원ㆍ환경경제연구
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    • 제21권3호
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    • pp.543-572
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    • 2012
  • 본 연구는 2000년부터 현재까지 한국과 일본의 에너지 수급 현황을 비교하는 한편, 2000년 이후 발표된 중장기 저탄소 에너지 계획 및 시나리오 관련 문헌들을 검토하였다. 에너지수급 측면에서 한국과 일본은 모두 에너지 수입의존도가 높고, OECD 국가들 중에서 제조업의 비중이 높으며, 전력 계통은 외부와 고립된 시스템이며, 발전량에서 원전이 차지하는 비중이 높고, 재생에너지 잠재량은 높지만 실제 생산량은 낮다는 점 등이 유사하다. 차이점은 에너지 소비량 추세가 일본은 감소하는 반면, 한국은 증가하고 있으며, 지역간 전력 교류가 한국은 가능한 반면, 일본은 그렇지 않으며, 향후 원자력 확대가 일본은 어려울 전망인 반면, 한국의 현 정부는 원자력 확대 방침을 유지하고 있다는 점 등이다. 후쿠시마 원전 사고 전후로, 일본과 한국의 정부에서 수립한 에너지계획은 원자력을 약 2배 수준으로 확대할 계획으로 하고 있었지만, 시민사회에서는 에너지 수요 저감, 원자력의 단계적 축소, 재생에너지 확대를 내용으로 하는 시나리오들을 발표하였다. 본 연구는 일본과 한국의 중장기 에너지 시나리오 및 계획 수립 연구에 활용될 수 있을 것이다.

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면진장치 적용을 고려한 원전구조물 생애주기 분석 (Life-Cycle Analysis of Nuclear Power Plant with Seismic Isolation System)

  • 김선용;이홍표;조명석
    • 한국전산구조공학회논문집
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    • 제26권6호
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    • pp.415-421
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    • 2013
  • 본 논문에서는 면진시스템이 원전에 적용될 경우 원전구조물의 생애주기 성능에 미치는 영향을 소개한다. 최근 내진설계와 더불어 강진발생 예상 지역에 적용을 목적으로 개발되는 면진시스템은 구조물을 장주기화하여 응답가속도를 줄이고 상대변위를 늘려줌으로써 구조물의 안전성을 증진시키는 것으로 알려져 있다. 따라서, 구조물의 안전성이 중요시되는 원전구조물에 면진시스템을 적용하기 위한 연구가 국내에서 진행 중에 있다. 본 연구에서는 원전구조물의 생애주기 성능분석에 있어서 특징을 분석하고, 면진시스템이 적용될 경우 원전구조물의 생애주기성능에 있어서 미치는 영향을 평가함으로써, 도출된 결과를 면진시스템 적용의 정량적인 타당성 평가에 활용할 수 있다.

동북아 해역 권원중첩수역 공동개발합의와 공동환경보호합의 도출 방안 (A Study on the Ways to Joint Marine Development and Joint Marine Environmental Protection in Northeast Asia)

  • 김기순
    • Strategy21
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    • 통권37호
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    • pp.193-241
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    • 2015
  • China, Japan and Korea are the world's top 10 energy consumers, and so very interested in the development of seabed hydrocarbon resources in order to meet their energy demands. The East China Sea is the tri-junction area where three countries' entitlements on the maritime boundaries are overlapped. There are abundant oil reserves in the East China Sea, and therefore competitions among countries are growing to get control of them. Although these countries have concluded the bilateral agreements to jointly develop resources in the East China Sea, they do not function as well. Because joint development and management of seabed petroleum resources can lead to stable development system, and to lower possibility of legal and political disputes, the needs for joint development agreement among three countries are urgent. Meanwhile, Northeast Asian seas are semi-closed seas, which are geographically closed and vulnerable to marine pollution. Moreover there are a lot of nuclear power plants in coastal area, and seabed petroleum resources are being developed. So it is likely to occur nuclear and oil spill accidents. Fukushima nuclear disaster and Bohai Bay oil spill accident in 2011 are the cases to exhibit the potential of major marine pollution accidents in this area. It is anticipated that the risks become higher because power plants and offshore oil platforms are extending gradually. Therefore, the ways to seek the joint marine environmental protection agreement focused on regulation of nuclear power plant and offshore oil platform have to be considered. In this paper, we try to find the way to make joint development and joint environmental protection agreement in Northeast Asian seas. We concentrate on the measure to drive joint development of seabed petroleum deposits in East China Sea's overlap area, despite of maritime delimitation and territorial disputes, and we try to drive joint marine environmental protection system to respond to marine pollution and accidents due to offshore oil platform and nuclear power plants. Through these consideration, we seek solutions to deal with lack of energy, disputes of maritime territorial and boundary delimitation, and marine pollution in Northeast Asia.