• Title/Summary/Keyword: 방사성액체폐기물

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Assessment of Cobalt Removal from Radioactive Liquid Waste Using Electrocoagulation (방사성 액체폐기물 내 코발트 제거를 위한 전기응집공법의 활용 가능성 평가)

  • Ko, Myoung-Soo;Kim, Yong-Tae;Kim, Young-Gwang;Kim, Kyoung-Woong
    • Economic and Environmental Geology
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    • v.51 no.2
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    • pp.177-183
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    • 2018
  • This study assessed an application of electrocoagulation (EC) for the removal of cobalt (Co) in radioactive liquid waste from nuclear power plant. The EC process is an electrochemical means to remove a contaminant in wastewater and a novel process to complement the disadvantage of chemical treatment and membrane process. Radioactive liquid waste has been produced from washing process of radio nuclide power plant cooling system. The EC process eliminates Co from the electrolyte within 10 min; in addition, the dewatered sludge produced in EC process is only 0.2 g. Therefore, the EC process is a promising technique for the removal of Co in radioactive liquid waste and volume reduction of wastes.

국내원전 액체방사성폐기물계통 설계경험

  • 이병식;김길정
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.43-47
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    • 2003
  • The performance of the Radwaste System is measured in terms of generation of waste volumes, the release of radioactive materials to the environment and the occupational radiation exposure to workers. Based on our design and operating experience from PWR plants, various design goals for liquid radwaste system were developed to improve system performance. It has been making continuous effort to develop the advanced liquid radwaste processing technology for new PWR plants since 1998. The primary goal of this effort was to obtain better performance and to design a more economical liquid radwaste system. This paper describes lesson learned experience from design of the liquid radwaste system in Korea Nuclear Power Plants.

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Uncertainty Analysis of the Calculated Radioactivity in Liquid Effluent Released as Batch Mode from a Nuclear Power Plant (발전용원자로에서 뱃치방식으로 배출되는 액체상 방사성물질의 방사능 평가결과에 대한 불확도 해석)

  • 정재학;박원재
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.562-571
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    • 2003
  • A series of factors such as sampling, pretreatment measurement, volume estimation which induces uncertainty of the calculated radioactivity in liquid effluent released from a nuclear power plant were analyzed. It is innately impossible to estimate exact error of the calculated radioactivity, since most of the input parameters are determined by a single measurement and true value of the released radioactivity cannot be known. In this paper, a systematic model to calculate uncertainty of the released liquid radioactivity was developed based upon the guidance report published by the ISO in 1993, and the model was applied to a set of hypothetical batch release conditions. As a result, the Priority of each input parameter was turned out to be (1) wastewater volume, (2) sample volume, and (3) measured radioactivity of the sample. In addition, probability distribution of the released radioactivity was simulated by Monte Carlo method combining the probability distribution of each input parameter It was shown that the radioactivity released to the environment, which has been reported as a single value, has a certain form of probability distribution.

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A study on decreasing the liquid waste and the liquid waste production status in HANARO (하나로의 액체 폐기물 발생 현황 및 저감 대책)

  • 강태진;황승렬;최호영
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.135-140
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    • 2003
  • The quantity of liquid waste produced during HANARO operation for the years from 1996 to 2002 has been investigated and the interrelation with the reactor power output has been analysed. The waste amount produced during this period was $263, 530{\ell}$ and the processing expense was 81, 690, 000 won. The waste amount and processing expense per reactor power output are $11.38{\ell}/MWD$ and 157 won/MWD, respectively. The waste has been reduced by improving repair work procedure and experiment process in the reactor hall.

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