A Study on the Structural Behavior of an Underground Radwaste Repository within a Granitic Rock Mass with a Fault Passing through the Cavern Roof

화장암반내 단층지역에 위치한 지하 방사성폐기물 처분장 구조거동연구

  • Published : 2001.09.01

Abstract

Numerical simulation is performed to understand the structural behavior of an underground radwaste repository, assumed to be located at the depth of 500 m, in a granitic rock mats, in which a fault intersects the roof of the repository cavern. Two dimensional universal distinct element code, UDEC is used in the analysis. The numerical model includes a granitic rock mass, a canister with PWR spent fuels surrounded by the compacted bentonite inside the deposition hole, and the mixed bentonite backfilled in the rest of the space within the repository cavern. The structural behavior of three different cases, each case with a fault of an angle of $33^{\circ},\;45^{\circ},\;and\;58^{\circ}$ passing through the cavern roof-wall intersection, has been compared. And then fro the case with the $45^{\circ}$ fault, the hydro-mechanical, thermo-mechanical, and thermo-hydro-mechanical interaction behavior have been studied. The effect of the time-dependent decaying heat, from the radioactive materials in PWR spent fuels, on the repository and its surroundings has been studied. The groundwater table is assumed to be located 10m below the ground surface, and a steady state flow algorithm is used.

지하 500 m의 화강암반내 단층지역에 위치한 지하 방사성폐기물 처분장의 구조거동을 이해하기 위하여 수치 해석을 수행하였다. 해석에는 2차원 해석코드인 UDEC을 사용하였다. 해석모델은 화강암반, 처분공내의 압축 벤토나이트로 둘러싸인 PWR 사용후 핵연료 처분용기 및 처분동굴내에 채워진 혼합 벤토나이트를 포함한다. 한 개의 단층이 처분동굴의 지붕과 벽이 만나는 지점을 33, 45, 및 $58^{\circ}$의 각도로 관통하는 세가지 다른 경우게 대한 구조거동을 비교, 분석하였다. 그리고 $45^{\circ}$단층의 경우에 대해서는 수리역학적, 열역학적, 및 열수리역학적 상호작용 거동을 해석하고 비교, 분석하였다. PWR 사용후 핵연료내의 방사성 물질로부터 나오는 시간의존 방사성 붕괴열에 의한 영향을 해석하였다. 지하수위는 지표면 아래 10 m로 가정하였고, 지하수해석은 정류 알고리즘을 사용하였다.

Keywords

References

  1. Preliminary conceptual design and performance assessment of a deep geological repository for high-level waste in the republic of Korea Kang, Chulhyung(et al)
  2. UDEC;Universal Distinct Element Code(version 3.0)
  3. in chief, Comprehensive Rock Engineering;surface and underground project case histories,(vol. 5) Hudson, J.A.(ed).
  4. Stripa Project 91-22 Distinct element modelling of joint behavior in nearfield rock Hokmark, H.;I. Israelsson
  5. Stripa Project 91-01 Distinct element method of fracture behavior in near field rock Hokmark, H.
  6. Report YJT-91-21, TVO, Helsinki, Finland Rock Mechanical, thermomechanical, and hydraulic behavior of the near field for spent nuclear fuel Johansson, E.;M. Hakala;L.J. Lorig.
  7. SKB Technical Report 93-3, Sweden Results from pre-investigations and detailed site characterizations;Summary Report, Aspo HRL-Geoscientific evaluation 1997/2
  8. Report YJT-93-06, TVO, Helsinki, Finland Application of the continuously yielding joint model for studying disposal of high-level nuclear waste in crystalline rock Hakala, M.;E. Johansson;A. Simonen;L. Lorig
  9. SKB Technical Report Results from pre-investigations and detailed site characterization;Summary Report, Aspo HRL-Geoscientific Evaluation 1997/2