• Title/Summary/Keyword: Low-and intermediate-level radioactive waste

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RADIATION SHIELDING EVALUATION OF IP-2 PACKAGES FOR LOW- AND INTERMEDIATE-LEVEL RADIOACTIVE WASTE

  • Kim, Min-Chul;Choi, Jong-Rak;Chung, Sung-Hwan;Ko, Jae-Hoon
    • Nuclear Engineering and Technology
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    • v.40 no.6
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    • pp.511-516
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    • 2008
  • Korea Hydro & Nuclear Power Co., Ltd. (KHNP) developed new IP-2 packages to transport low- and intermediate-level radioactive waste (LILW) steel drums from nuclear power plants to a disposal facility in accordance with IAEA and Korean transport regulations of radioactive material. Radiation shielding evaluation of the packages was carried out to demonstrate compliance with the regulatory requirements for IP-2 packages of radioactive material. Dose rate limits of LILW drums contained in the packages were determined.

WOLSONG LOW- AND INTERMEDIATE-LEVEL RADIOACTIVE WASTE DISPOSAL CENTER: PROGRESS AND CHALLENGES

  • Park, Jin-Beak;Jung, Hae-Ryong;Lee, Eun-Young;Kim, Chang-Lak;Kim, Geon-Young;Kim, Kyung-Su;Koh, Yong-Kwon;Park, Kyung-Woo;Cheong, Jae-Hak;Jeong, Chan-Woo;Choi, Jong-Soo;Kim, Kyung-Deok
    • Nuclear Engineering and Technology
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    • v.41 no.4
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    • pp.477-492
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    • 2009
  • In this paper, we discuss the experiences during the preparation of the Wolsong Low- and Intermediate-Level Radioactive Waste Disposal Center. These experiences have importance as a first implementation for the national LILW disposal facility in the Republic of Korea. As for the progress, it relates to the area of selected disposal site, the disposal site characteristics, waste characteristics of the disposal facility, safety assessment, and licensing process. During these experiences, we also discuss the necessity for new organization and change for a radioactive waste management system. Further effort for the safe management of radioactive waste needs to be pursued.

Disposal Approach for Long-lived Low and Intermediate-Level Radioactive Waste (장반감기 중저준위 방사성 폐기물의 국외 처분동향과 처분방안)

  • Park, Jin-Beak;Park, Joo-Wan;Kim, Chang-Lak
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • pp.143-152
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    • 2005
  • There certainly exists the radioactive inventory that exceeds the waste acceptance criteria for final disposal of the low and intermediate-level radioactive waste. In this paper, current disposal status of the long-lived radioactive waste in several nations are summarized and the basic procedures for disposal approach are suggested. With this suggestion, intensive discussion and research activities can hopefully be launched to set down the possible resolutions to dispose of the long-lived radioactive 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.

Characterization of Glass Melts Containing Simulated Low and Intermediate Level Radioactive Waste

  • Jung, Hyun-Su;Kim, Ki-Dong;Lee, Seung-Heon;Kwon, Sung-Ku;Kim, Cheon-Woo;Park, Jong-Kil;Hwang, Tae-Won;Ahn, Zou-Sam
    • Journal of the Korean Ceramic Society
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    • v.43 no.3
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    • pp.148-151
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    • 2006
  • In order to examine the process parameters for the vitrification of Low and Intermediate Level radioactive Waste (LILW) generated from nuclear power plants, measurements of several melt properties was performed for four selected glasses containing simulated waste. Electrical conductivity and viscosity were determined at temperatures ranging from 1123 to $1673^{\circ}C$. The temperature dependences of both properties in the molten state showed a similar behavior in which their values decrease as the temperature increases. The values of the electrical conductivity and viscosity at a temperature of 1423K adopted in an induction cold crucible melter process were $0.27{\sim}0.42$ S/cm and $9.8{\sim}42$ dPas, respectively.

Development of the Safety Assessment Code (CALM) for the Disposal of Low-and Intermediate-Level Radioactive Waste (중ㆍ저준위 방사성폐기물 처분안정성 평가코드(CALM) 개발)

  • Han, Kyong-Won;Cho, Won-Jin;Lee, Han-Soo;Lee, Youn-Myoung;Park, Hee-Sung;Suh, Kyung-Suk;Park, Heu-Joo-;Park, Hun-Hwee
    • Nuclear Engineering and Technology
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    • v.22 no.1
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    • pp.36-44
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    • 1990
  • A safety assessment computer code CALM (Computer program of Assessment for LILW Management) is developed for the theoretical prediction of long-term safety of low-and intermediate-level radioactive waste disposal. CALM is composed of three submodels, which are the resaturation model, the geosphere migration model, and the radiation dose model. For the verification of its usefulness, the safety assessment of an assumed waste repository is performed. The results show that the computer code, CALM developed through this study can be a useful tool for the safety assessment of low- and intermediate-level radioactive waste repository.

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Performance Assessment of Engineered Barrier for Retardation of Radionuclide Release in a Low- and Intermediate-Level Radioactive Waste Repository (중저준위방사성폐기물 처분장 인공방벽의 핵종유출 저지능 평가)

  • W.J. Cho;Lee, J.O.;P.S. Hahn;Park, H.H.
    • Nuclear Engineering and Technology
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    • v.25 no.3
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    • pp.447-456
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    • 1993
  • A simplified model to assess the performance of engineered barrier for the retardation of radionuclide release in a low- and intermediate-level radioactive waste repository was developed. The model is based on the repository design concept being suggested in Korea, and considers two types of release scenario ; a design-bas release for the design of engineered barrier and a realistic release for the performance assessment. For the numerical illustration, the sample calculations were performed for five radionuclides with different chemical characteristics, and the results were analyzed.

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Development of a Quality Assurance Safety Assessment Database for Near Surface Radioactive Waste Disposal

  • Park J.W.;Kim C.L.;Park J.B.;Lee E.Y.;Lee Y.M.;Kang C.H.;Zhou W.;Kozak M.W.
    • Nuclear Engineering and Technology
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    • v.35 no.6
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    • pp.556-565
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    • 2003
  • A quality assurance safety assessment database, called QUARK (QUality Assurance Program for Radioactive Waste Management in Korea), has been developed to manage both analysis information and parameter database for safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility in Korea. QUARK is such a tool that serves QA purposes for managing safety assessment information properly and securely. In QUARK, the information is organized and linked to maximize the integrity of information and traceability. QUARK provides guidance to conduct safety assessment analysis, from scenario generation to result analysis, and provides a window to inspect and trace previous safety assessment analysis and parameter values. QUARK also provides default database for safety assessment staff who construct input data files using SAGE(Safety Assessment Groundwater Evaluation), a safety assessment computer code.