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RISS 인기검색어
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- 저자 : Juyub Kim (검색결과 6 건)
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Jaewon Park,Juyub Kim,Hyungi Byun 한국방사성폐기물학회 2022 한국방사성폐기물학회 학술논문요약집 Vol.20 No.2
Decommissioning of a nuclear power plant (NPP) generate large amounts of various types of wastes. In accordance with the Nuclear Safety and Security Commission Notice of Korea (No. 2020- 6), they are classified as High Level Waste (HLW), Intermediate Level Waste (ILW), Low Level Waste (LLW), Very Low Level Waste (VLLW) and Exempt Waste (EW) according to specific activities. More than 90% of the wastes are at exempt level, mostly metal and concrete wastes with low radioactivity, of which the concentrations of nuclides is less than the allowable concentration of self-disposal. The self-disposal or recycling of these wastes is widely used worldwide. More than 10,000 drums, based on 200 L drum, are expected to be produced in the decommissioning process of a unit of nuclear power plant. Due to the limited storage capacity of the intermediate & low level waste disposal facility in Gyeongju, recycling and self-disposal of EW are actively recommended in Korea. A variety of scenarios were proposed for recycling and self-disposal of decommissioning metal/ concrete wastes, and a computational program called REDISA was developed to perform the dose evaluation for each recycling and self-disposal scenario. The REDISA computer program can calculate external and internal exposure doses by simulating the exposure pathways from waste generation, thru transport, processing, manufacture, to the final destination of recycling or self-disposal. In this study, the self-disposal scenario was only considered for the dose evaluation. Many studies have been conducted to evaluate the exposure doses of the radioactive waste disposal sites. However, there have been few researches on dose evaluation for self-disposal landfills. In particular, the dose evaluation is important not only during the operation period, but also for a long period after the facility is closed. To this end, we developed a conceptual model for dose evaluation for post-closure scenarios of the self-disposal landfill of decommissioning metal/concrete wastes with reference to the methodology of IAEA-TECDOC-1380. The model incorporates three exposure pathways, including external exposure from contaminated soil, internal exposure by inhalation, and internal exposure by ingestion of water and food grown in contaminated soil. The duration of the dose evaluation is set to 100,000 years after the closure of landfill facility. Co-60 was selected as dominant nuclide, and dose evaluation was performed based on unit specific activity of 1 Bq/g. Exposure doses shall be verified for their application in accordance with the annual dose limit of 10 ?Sv/yr for self-disposal. As a result, the post-closure scenario of selfdisposal landfills have shown negligible effects on public health, which means that the exposures doses from transportation and operational processes should be considered more carefully for selfdisposal of decommissioning metal/concrete wastes.
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Gas Migration in Low- and Intermediate-Level Waste (LILW) Disposal Facility in Korea
Jaechul Ha,Jeong-Hwan Lee,Haeryong Jung,Juyub Kim,Juyoul Kim 한국방사성폐기물학회 2014 방사성폐기물학회지 Vol.12 No.4
본 연구에서는 중·저준위방사성폐기물 처분시설(이하 처분시설)에서 발생하는 기체의 이동현상을 예측하기 위한 2차원 수 치 모델링을 수행하였다. 또한, 기체 이동 모델링에서 주요 입력변수로 적용되는 사일로 콘크리트의 기체침투압(gas entry pressure)와 기체 투과도(gas permeability)를 실측하여, 모델링 입력변수로 적용하였다. 사일로 콘크리트의 기체침투압(gas entry pressure)와 기체 투과도(gas permeability)는 각각 0.97±0.15 bar 및 2.44×10-17 m2로 측정되었다. 기체 이동 모델링 결과, 사일로 내부에서 발생하는 수소 기체는 기상으로 이동하지 않고 지하수에 용해되어 지하수와 함께 생태계로 이동하는 것을 알 수 있다. 또한, 폐쇄 후 약 1,000 년 후 부터 사일로 상부부터 수소기체 밀도가 증가하기 시작하는 것으로 예측되었 다. 따라서, 사일로 내부에서 발생된 기체는 기상으로 사일로 내부에 축적되지 않으며, 이로 인해 사일로 콘크리트의 내구성 에 영향을 미치지 않을 것으로 판단된다. The first Low- and Intermediate-Level Waste (LILW) disposal facility with 6 silos has been constructed in granite host rock saturated with groundwater in Korea. A two-dimensional numerical modeling on gas migration was carried out using TOUGH2 with EOS5 module in the disposal facility. Laboratory-scale experiments were also performed to measure the important properties of silo concrete related with gas migration. The gas entry pressure and relative gas permeability of the concrete was determined to be 0.97±0.15 bar and 2.44×10-17 m2, respectively. The results of the numerical modeling showed that hydrogen gas generated from radioactive wastes was dissolved in groundwater and migrated to biosphere as an aqueous phase. Only a small portion of hydrogen appeared as a gas phase after 1,000 years of gas generation. The results strongly suggested that hydrogen gas does not accumulate inside the disposal facility as a gas phase. Therefore, it is expected that there would be no harmful effects on the integrity of the silo concrete due to gas generation.
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하재철,이정환,정해룡,김주엽,김주열,Ha, Jaechul,Lee, Jeong-Hwan,Jung, Haeryong,Kim, Juyub,Kim, Juyoul 한국방사성폐기물학회 2014 방사성폐기물학회지 Vol.12 No.4
본 연구에서는 중 저준위방사성폐기물 처분시설(이하 처분시설)에서 발생하는 기체의 이동현상을 예측하기 위한 2차원 수치 모델링을 수행하였다. 또한, 기체 이동 모델링에서 주요 입력변수로 적용되는 사일로 콘크리트의 기체침투압(gas entry pressure)와 기체 투과도(gas permeability)를 실측하여, 모델링 입력변수로 적용하였다. 사일로 콘크리트의 기체침투압(gas entry pressure)와 기체 투과도(gas permeability)는 각각 $0.97{\pm}0.15bar$ 및 $2.44{\times}10^{-17}m^2$로 측정되었다. 기체 이동 모델링 결과, 사일로 내부에서 발생하는 수소 기체는 기상으로 이동하지 않고 지하수에 용해되어 지하수와 함께 생태계로 이동하는 것을 알 수 있다. 또한, 폐쇄 후 약 1,000 년 후 부터 사일로 상부부터 수소기체 밀도가 증가하기 시작하는 것으로 예측되었다. 따라서, 사일로 내부에서 발생된 기체는 기상으로 사일로 내부에 축적되지 않으며, 이로 인해 사일로 콘크리트의 내구성에 영향을 미치지 않을 것으로 판단된다. The first Low- and Intermediate-Level Waste (LILW) disposal facility with 6 silos has been constructed in granite host rock saturated with groundwater in Korea. A two-dimensional numerical modeling on gas migration was carried out using TOUGH2 with EOS5 module in the disposal facility. Laboratory-scale experiments were also performed to measure the important properties of silo concrete related with gas migration. The gas entry pressure and relative gas permeability of the concrete was determined to be $0.97{\pm}0.15bar$ and $2.44{\times}10^{-17}m^2$, respectively. The results of the numerical modeling showed that hydrogen gas generated from radioactive wastes was dissolved in groundwater and migrated to biosphere as an aqueous phase. Only a small portion of hydrogen appeared as a gas phase after 1,000 years of gas generation. The results strongly suggested that hydrogen gas does not accumulate inside the disposal facility as a gas phase. Therefore, it is expected that there would be no harmful effects on the integrity of the silo concrete due to gas generation.
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