• Title/Summary/Keyword: 중.저준위

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Preparation and Management of the Input Data for the Safety Assessment of Low- and Intermediate-level Radioactive Waste Disposal Facility in Korea (중·저준위 방사성폐기물 처분시설 안전성평가를 위한 입력데이터 설정 및 관리에 대한 고찰)

  • Park, Jin Beak;Kim, Hyun-Joo;Lee, Dong-Hee
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.12 no.4
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    • pp.345-361
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    • 2014

  • The systematic quality assurance activities on documents of the safety assessment are required for the safety case of the low- and intermediate-level radioactive waste disposal facility. In this paper, quality assurance system focused on the input data including the site characterization, groundwater flow, system design and monitoring are prepared and discussed. Rule for the input data selection is suggested and applied for the safety assessment which is based on the in-situ/experiment observations, final facility design and waste pileup plan, engineered barrier, field monitoring, recent biosphere, and radionuclide inventory. The reduction of data uncertainty will be expected to contribute to the safety of disposal facility further.

  • https://doi.org/10.7733/jnfcwt.2014.12.4.345 인용 PDF KSCI KPUBS HTML

Analysis of the statistical properties for the background fractures in the LILW disposal site of Korea (중.저준위 방사성폐기물 처분 부지 내 배경 단열의 통계적 특성 분석)

  • Ji, Sung-Hoon;Park, Kyung-Woo;Kim, Kyoung-Su;Kim, Chun-Soo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.6 no.4
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    • pp.257-263
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    • 2008

  • We analyzed the statistical properties for the conductive background fractures in the Low and Intermediate Level Waste(LILW) disposal site to conceptualize of its groundwater flow system. The background fractures were classified to fracture sets based on their trends and plunges that were obtained from the borehole logging data, and then the fracture transmissivity distribution was inferred from the fixed interval hydraulic test results. The fracture size distribution of each fracture set was estimated using the fracture density and fracture mapping data. To verify the analyzed results, we compared observed field data to simulated one from the DFN model that was constructed with the analyzed statistical properties of the background fractures, and they showed a good agreement.

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Analysis of Case Studies on Experimental Research of Gas Generation in Foreign Countries for Low- and Intermediate-level Radioactive Waste Disposal (중.저준위 방사성폐기물 처분을 위한 국외 기체발생 실증실험시설 운영사례 분석)

  • Park, Jin-Beak;Lee, Sun-Joung;Kim, Suk-Hoon;Kim, Ju-Youl
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.8 no.3
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    • pp.229-238
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    • 2010

  • In order to acquire a realistic forecast for the lifetime and post-closure period of the LILW (Low- and Intermediate-Level Radioactive Waste) repository and to establish the overall management plan associated gas issues. it is essential to carry out the long-term experimental research in a similar condition to actual disposal environment. Regarding this, as a part of the following-up actions on a construction and operation license for the first stage of the LILW repository at Gyeongju city, a large-scale in-situ experiment is being planned. For securing basic data on the experiment, the experimental researches related to gas generation previously performed in foreign countries are reviewed in detail. Consequently, it is judged that data on the gas generation experiment in Finland could be practically applied as the benchmark for our large-scale in-situ experiment because the same disposal concept as the Korean repository is adopted and the experiment is performed in a scale large enough to allow the use of regular waste packages.

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