논문 상세보기

Preliminary Study on Fluid Flow and Radionuclide Transport in Generic Repository Located at Fractured Crystalline Rock

  • 언어ENG
  • URLhttps://db.koreascholar.com/Article/Detail/430431
모든 회원에게 무료로 제공됩니다.
한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
초록

With the increase of temporarily-stored spent radioactive fuels, there is an increasing necessity for the safe disposal of high-level radioactive waste (HLW). Among various methods for the disposal of HLW, a deep geological disposal system is adapted as a HLW disposal strategy in many countries. Before the construction of a repository in deep geological condition, a performance assessment, which means the use of numerical models to simulate the long-term behavior of a multi-barrier system in HLW repository, has been widely performed to ensure the isolation of radionuclides from human and related environments for more than a million years. Meanwhile, Korea Atomic Energy Research Institute (KAERI) is developing a process-based total system performance assessment framework for a geological disposal system (APro). To improve the reliability of APro, KAERI is participating in DECOVALEX-2023 Task F, which is the international joint program for the comparison of the models and methods used in deep geological performance assessment. As a final goal of Task F, the reference case for a generic repository in fractured crystalline rock is described. The three-dimensional generic repository is located in a domain of 5 km in length, 2 km in width, and 1 km in depth, and contains an engineering barrier system with 2,500 deposition holes in fractured crystalline rock. In this study, a numerical simulation of the reference case is performed with COMSOL Multiphysics as a part of Task F. The fractured crystalline rock is described with the discrete fracture matrix (DFM) model, which expresses major deterministic fractures explicitly in the domain and minor stochastic fractures implicitly with upscaled quantities. As an output of the numerical simulation, fluid flow at steady-state and radionuclide transport are evaluated for ~106 years. The result shows that fractures dominate the transport of radionuclides due to much higher hydraulic properties than rock matrix. The numerical modeling approaches used in this study are expected to provide a basis for performance assessment of nuclear waste disposal repository located in fractured crystalline rock.

저자
  • Yong-Min Kim(Korea Atomic Energy Research Institute, 111, Daedeokdae-ro 989 eongil, Yuseong-gu, Daejeon) Corresponding author
  • Jaewon Lee(Korea Atomic Energy Research Institute, 111, Daedeokdae-ro 989 eongil, Yuseong-gu, Daejeon)
  • Sung-Hoon Ji(Korea Atomic Energy Research Institute, 111, Daedeokdae-ro 989 eongil, Yuseong-gu, Daejeon)
  • Jung-Woo Kim(Korea Atomic Energy Research Institute, 111, Daedeokdae-ro 989 eongil, Yuseong-gu, Daejeon)