• Title/Summary/Keyword: Low level waste

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Development of a Computer Code for Low-and Intermediate-Level Radioactive Waste Disposal Safety Assessment

  • Park, J.W.;Kim, C.L.;Lee, E.Y.;Lee, Y.M.;Kang, C.H.;Zhou, W.;Kozak, M.W.
    • Journal of Radiation Protection and Research
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    • v.29 no.1
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    • pp.41-48
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    • 2004

  • A safety assessment code, called SAGE (Safety Assessment Groundwater Evaluation), has been developed to describe post-closure radionuclide releases and potential radiological doses for low- and intermediate-level radioactive waste (LILW) disposal in an engineered vault facility in Korea. The conceptual model implemented in the code is focused on the release of radionuclide from a gradually degrading engineered barrier system to an underlying unsaturated zone, thence to a saturated groundwater zone. The radionuclide transport equations are solved by spatially discretizing the disposal system into a series of compartments. Mass transfer between compartments is by diffusion/dispersion and advection. In all compartments, radionuclides ate decayed either as a single-member chain or as multi-member chains. The biosphere is represented as a set of steady-state, radionuclide-specific pathway dose conversion factors that are multiplied by the appropriate release rate from the far field for each pathway. The code has the capability to treat input parameters either deterministically or probabilistically. Parameter input is achieved through a user-friendly Graphical User Interface. An application is presented, which is compared against safety assessment results from the other computer codes, to benchmark the reliability of system-level conceptual modeling of the code.

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An Introduction to the Expansion Plan of the Underground Repository of Low- and Intermediate-level Radioactive Waste In Forsmark, Sweden (스웨덴 포쉬마크 중저준위 방사성 폐기물 지하 처분장 확장 계획 소개)

  • Kwon, Saeha;Min, Ki-Bok;Stephansson, Ove
    • Tunnel and Underground Space
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    • v.26 no.5
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    • pp.339-347
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    • 2016

  • The world's first underground repository for low- and intermediate- level radioactive waste (SFR1) has been in operation since 1988. SFR1 can accommodate $1,000m^3$ of radioactive waste per year with 4 chambers and 1 silo with a total capacity of $63,000m^3$ of radioactive waste. With extended operation time of 10 of the 12 nuclear power reactors and dismantling of the other 2 nuclear reactors, more nuclear waste need to be disposed in the future. Therefore, Swedish Nuclear Fuel and Waste Management Company (SKB) submitted a license application for a repository extension (SFR3) that consists of 6 additional rock chambers with a capacity of $108,000m^3$ of radioactive waste and for accommodating 9 boiling water reactor tanks. In this study, plans for the extension SFR3 are presented with the geological, geomechanical and hydrogeological issues to be considered.

  • https://doi.org/10.7474/TUS.2016.26.5.339 인용 PDF KSCI