• Title/Summary/Keyword: Double layered repository

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Analyses of the Double-Layered Repository Concepts for Spent Nuclear Fuels (사용후핵연료 심지층 처분장 복층개념 분석)

  • Lee, Jongyoul;Kim, Hyeona;Lee, Minsoo;Choi, Heui-Joo;Kim, Kyungsu
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.15 no.2
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    • pp.151-159
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    • 2017
  • A deep geological disposal at a depth of 500 m in stable host rock is considered to be the safest method with current technologies for disposal of spent fuels classified as high-level radioactive waste. The most important requirement is that the temperature of the bentonite buffer, which is a component of the engineered barrier, should not exceed $100^{\circ}C$. In Korea, the amount of spent fuel generated by nuclear power generation, which accounts for about 30% of the total electricity, is continuously increasing and accumulating. Accordingly, the area required to dispose of it is also increasing. In this study, various duplex disposal concepts were derived for the purpose of improving the disposal efficiency by reducing the disposal area. Based on these concepts, thermal analyses were carried out to confirm whether the critical disposal system requirements were met, and the thermal stability of the disposal system was evaluated by analyzing the results. The results showed that upward 75 m or downward 75 m apart from the reference disposal system location of 500 m depth would qualify for the double layered disposal concept. The results of this study can be applied to the establishment of spent fuel management policy and the design of practical commercial disposal system. Detailed analyses with data of a real disposal site are necessary.

A Numerical Model for Nuclide Migration in the Far-field of the Repository (처분장 Far-field에서의 핵종이동 수치 모델)

  • Lee, Youn-Myoung;Lee, Han-Soo;Park, Heui-Joo;Cho, Won-Jin;Han, Kyong-Won;Park, Hun-Hwee
    • Nuclear Engineering and Technology
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    • v.21 no.4
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    • pp.267-276
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    • 1989
  • A numerical model for nuclide migration through fractured rock media has been developed. Nuclide transport with groundwater in rock fissures and the diffusion of nuclides into rock matrix are considered one-dimensionally . In the safety assessment of the repository for radioactive waste, this one-dimensional model by the finite-difference scheme, which enables us not only to use more realistic boundary conditions but also to model the nonhomogeneous rock medium as the multilayered media, can be used effectively with the analytical mode. The solution by the numerical model will be verified analytically, and then extended to the double-layered rock medium transport model.

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