• 제목/요약/키워드: Fukushima nuclear power plant

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The effect of the number of subintervals upon the quantification of the seismic probabilistic safety assessment of a nuclear power plant

  • Ji Suk Kim;Man Cheol Kim
    • Nuclear Engineering and Technology
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    • 제55권4호
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    • pp.1420-1427
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    • 2023
  • Seismic risk has received increased attention since the 2011 Fukushima accident in Japan. The seismic risk of a nuclear power plant is evaluated via seismic probabilistic safety assessment (PSA), for which several methods are available. Recently, the discrete approach has become widely used. This approximates the seismic risk by discretizing the ground motion level interval into a small number of subintervals with the expectation of providing a conservative result. The present study examines the effect of the number of subintervals upon the results of seismic risk quantification. It is demonstrated that a small number of subintervals may lead to either an underestimation or overestimation of the seismic risk depending on the ground motion level. The present paper also provides a method for finding the boundaries between overestimation and underestimation regions, and illustrates the effect of the number of subintervals upon the seismic risk evaluation with an example. By providing a method for determining the effect of a small number of subintervals upon the results of seismic risk quantification, the present study will assist seismic PSA analysts to determine the appropriate number of subintervals and to better understand seismic risk quantification.

방사능 관련 일본산 수산물 수입 분쟁에 관한 SPS 협정 분석 (A Critical Analysis of the SPS Dispute over the Import Ban on Japanese Radioactive Seafood)

  • 윤정현;임송수
    • 무역학회지
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    • 제44권4호
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    • pp.19-34
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    • 2019
  • This study investigates the WTO dispute over Japanese fishery products originated from Fukushima and another seven prefectures. Being subject to an import ban and additional radioactive test requirements, Japan complained that the Korean government's trade measures are inconsistent with the principles of the Agreement on Sanitary and Phytosanitary Measures. This paper considered the contrasting judicial decisions made by the Panel and Appellate Body and analyzed the debates with respect to their trade-discriminatory effects (Article 2.4), the relevance of appropriate level of protection (Article 5.6) and the precautionary approaches (Article 5.7). Consistent with the final rulings, this paper identifies the need for a broaden understanding of regional conditions and qualitative aspects of protection in risk analysis. Findings also suggest that Korea has diverted its fishery imports from Japan to other countries, while Japan has created export diversion from Korea to other destinations.

Sentiment analysis of nuclear energy-related articles and their comments on a portal site in Rep. of Korea in 2010-2019

  • Jeong, So Yun;Kim, Jae Wook;Kim, Young Seo;Joo, Han Young;Moon, Joo Hyun
    • Nuclear Engineering and Technology
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    • 제53권3호
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    • pp.1013-1019
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    • 2021
  • This paper reviewed the temporal changes in the public opinions on nuclear energy in Korea with a big data analysis of nuclear energy-related articles and their comments posted on the portal site NAVER. All articles that included at least one of "nuclear energy," "nuclear power plant (NPP)," "nuclear power phase-out," or "anti-nuclear" in their titles or main text were extracted from those posted on NAVER in January 2010-December 2019. First, we performed annual word frequency analysis to identify what words had appeared most frequently in the articles. For that period, the most frequent words were "NPP," "nuclear energy," and "energy." In addition, "safety" has remained in the upper ranks since the Fukushima NPP accident. Then, we performed sentiment analysis of the pre-processed articles. The sentiment analysis showed that positive-tone articles have been reported more frequently than negativetone over the entire analysis period. Last, we performed sentiment analysis of the comments on the articles to examine the public's intention regarding nuclear issues. The analysis showed that the number of negative comments to articles each month-irrespective of positive or negative tone-was always larger than that of positive comments over the entire analysis period.

원전 사고지역에서 실내대피를 위한 임시대피시설의 거주성 확보방안 (Measures to Secure the Habitability of Temporary Shelter for Shelter in Place in Nuclear Power Plant Accidents)

  • 김정동;은종화
    • 한국재난정보학회 논문집
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    • 제19권3호
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    • pp.582-596
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    • 2023
  • 연구목적: 본 연구는 원전사고 발생 시 임시 대피시설의 안전성을 강화할 수 있는 방안을 연구하였다. 연구방법: 본 연구에서는 과거의 체르노빌, 후쿠시마, 쓰리마일섬(TMI) 원전사고에 대한 사례연구를 활용하였다. 연구결과: 현재의 방사선 비상 대응 계획은 소개에 중점을 두고 있으며, 실내대피 개념은 단순히 주민 대피를 지원하는 수단으로 활용되고 있다. 그러나 사례연구를 통해 INES-5 이상의 사고의 경우, 소개보다 실내대피를 장려하는 것이 사상자 최소화에 효과적임을 확인하였다. 더 나은 실내대피를 보장하기 위해 아파트를 임시 대피소로 활용할 것을 권장하며, 아파트가 방사선 방호 기술을 갖추도록 개선사항을 제안한다. 결론: 더 나은 실내대피를 보장하기 위해 아파트를 임시 대피소로 활용할 것을 권장하며, 차폐, 양압, 밀폐기술을 이용해서 아파트의 성능을 보완하고자 한다.

System dynamics simulation of the thermal dynamic processes in nuclear power plants

  • El-Sefy, Mohamed;Ezzeldin, Mohamed;El-Dakhakhni, Wael;Wiebe, Lydell;Nagasaki, Shinya
    • Nuclear Engineering and Technology
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    • 제51권6호
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    • pp.1540-1553
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    • 2019
  • A nuclear power plant (NPP) is a highly complex system-of-systems as manifested through its internal systems interdependence. The negative impact of such interdependence was demonstrated through the 2011 Fukushima Daiichi nuclear disaster. As such, there is a critical need for new strategies to overcome the limitations of current risk assessment techniques (e.g. the use of static event and fault tree schemes), particularly through simulation of the nonlinear dynamic feedback mechanisms between the different NPP systems/components. As the first and key step towards developing an integrated NPP dynamic probabilistic risk assessment platform that can account for such feedback mechanisms, the current study adopts a system dynamics simulation approach to model the thermal dynamic processes in: the reactor core; the secondary coolant system; and the pressurized water reactor. The reactor core and secondary coolant system parameters used to develop system dynamics models are based on those of the Palo Verde Nuclear Generating Station. These three system dynamics models are subsequently validated, using results from published work, under different system perturbations including the change in reactivity, the steam valve coefficient, the primary coolant flow, and others. Moving forward, the developed system dynamics models can be integrated with other interacting processes within a NPP to form the basis of a dynamic system-level (systemic) risk assessment tool.

Looking Back over a Decade "Final Decision Call after the Accidents of the Fukushima Nuclear Power Plant"

  • Nakajima, Isao;Kurokawa, Kiyoshi
    • Journal of Multimedia Information System
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    • 제7권2호
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    • pp.147-156
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    • 2020
  • The author Nakajima was involved in the field of disaster communications and emergency medical care as guest research scientist at the Fukushima Nuclear Accident Independent Investigation Commission established by the National Diet of Japan and reviewer of the Commission's report, and Kurokawa was the chairman of this Commission. Looking back over a decade, we are on the liability issue of bureaucrats and telecom operators, so it's becoming clear what was hidden at the time. The battery of NTT DoCoMo's mobile phone repeaters had a capacity of only about 24 hours, and communication failures increased after one day. The Government also failed to issue an announcement of "Vent from reactor" under the Telecommunications Act Article No. 129. This mistake lost the opportunity to use the third-party telecommunications (e.g. taxi radios). Furthermore, as a result of LASCOM (telecommunications satellite network for local governments via GEO) and a variety of unexpected communication failures, the evacuation order "Escape!" could not be notified to the general public well. As a result, the general public was exposed to unnecessary radiation exposure. Such bureaucratic slow action in emergencies is common in the response to the 2020 coronavirus.

마코프 모델을 이용한 원전 비상 통신 시스템 성능 분석 (Performance Analysis of Emergency Communication System of Nuclear Power Plant using Markov Model)

  • 손광섭
    • 전자공학회논문지
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    • 제51권3호
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    • pp.10-21
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    • 2014
  • 후쿠시마 원전사고는 자연재해에 의한 중대사고 발생 시 전원공급 중단 및 극한 환경으로 인해 발전소 내부 상황을 정확하게 파악하지 못하였고, 대부분의 계측제어시스템이 그 기능을 제대로 발휘하지 못해 비상냉각기능이 상실되어 수소폭발 및 다량의 방사능이 누출된 사고였다. 본 논문에서는 중대사고 발생 시에도 발전소 내부 상황을 감시하고, 적절히 제어할 수 있는 비상대응시스템에 대하여 소개하고, 비상대응시스템에 사용되는 무선통신망의 성능요구사항에 대해서 논의하고, 요구사항을 만족시킬 수 있는 비상통신망의 성능을 마코프 모델을 이용하여 분석하였다.

대규모 지진해일로 인한 침수 및 배수 시스템 프레임워크에 대한 연구 (Flooding and recovery system framework for Tsunami)

  • Lee, Sun Kee
    • 시스템엔지니어링학술지
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    • 제8권2호
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    • pp.47-55
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    • 2012
  • Tsunami disaster, which ruined Japan Fukushima nuclear power plant sites in 2011 March, has raised not only the perception of that Tsunami and/or large scale flooding possibly surpass the design baselines for industry facilities and plants, but also the necessity to establish recovery system against flooding. This study suggests the framework for flooding and drainage system in compliance with flooding and drainage concept to define and identify requirements, functions, and components of the system with traceable relations. The framework with combination to CMMI engineering process is the base of corresponding high level system design.

Study on multi-stage magnetic separation device for paramagnetic materials operated in low magnetic fields

  • F. Mishima;Aoi Nagahama;N. Nomura;S. Nishijima
    • 한국초전도ㆍ저온공학회논문지
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    • 제25권3호
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    • pp.13-17
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    • 2023
  • Magnetic separation technology for small paramagnetic particles has been desired for the volume reduction of contaminated soil from the Fukushima nuclear power plant accident and for the separation of scale and crud from nuclear power plants. However, the magnetic separation for paramagnetic particles requires a superconducting high gradient magnetic separation system applied, hence expanding the bore diameter of the magnets is necessary for mass processing and the initial and running costs would be enormous. The use of high magnetic fields makes safe onsite operation difficult, and there is an industrial need to increase the magnetic separation efficiency for paramagnetic particles in as low a magnetic field as possible. Therefore, we have been developing a magnetic separation system combined with a selection tube, which can separate small paramagnetic particles in a low magnetic field. In the previous technique we developed, a certain range of particle size was classified, and the classified particles were captured by magnetic separation. In this new approach, the fluid control method has been improved in order to the selectively classify particles of various diameters by using a multi-stage selection tube. The soil classification using a multi-stage selection tube was studied by calculation and experiment, and good results were obtained. In this paper, we report the effectiveness of the multi-stage selection tube was examined.

PRESENT DAY EOPS AND SAMG - WHERE DO WE GO FROM HERE?

  • Vayssier, George
    • Nuclear Engineering and Technology
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    • 제44권3호
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    • pp.225-236
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    • 2012
  • The Fukushima-Daiichi accident shook the world, as a well-known plant design, the General Electric BWR Mark I, was heavily damaged in the tsunami, which followed the Great Japanese Earthquake of 11 March 2011. Plant safety functions were lost and, as both AC and DC failed, manoeuvrability of the plants at the site virtually came to a full stop. The traditional system of Emergency Operating Procedures (EOPs) and Severe Accident Management Guidelines (SAMG) failed to protect core and containment, and severe core damage resulted, followed by devastating hydrogen explosions and, finally, considerable radioactive releases. The root cause may not only have been that the design against tsunamis was incorrect, but that the defence against accidents in most power plants is based on traditional assumptions, such as Large Break LOCA as the limiting event, whereas there is no engineered design against severe accidents in most plants. Accidents beyond the licensed design basis have hardly been considered in the various designs, and if they were included, they often were not classified for their safety role, as most system safety classifications considered only design basis accidents. It is, hence, time to again consider the Design Basis Accident, and ask ourselves whether the time has not come to consider engineered safety functions to mitigate core damage accidents. Associated is a proper classification of those systems that do the job. Also associated are safety criteria, which so far are only related to 'public health and safety'; in reality, nuclear accidents cause few casualties, but create immense economical and societal effects-for which there are no criteria to be met. Severe accidents create an environment far surpassing the imagination of those who developed EOPs and SAMG, most of which was developed after Three Mile Island - an accident where all was still in place, except the insight in the event was lost. It requires fundamental changes in our present safety approach and safety thinking and, hence, also in our EOPs and SAMG, in order to prevent future 'Fukushimas'.