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

  • Park, J.W. (Nuclear Environment Technology Institute, Korea Hydro & Nuclear Power Co., Ltd.) ;
  • Kim, C.L. (Nuclear Environment Technology Institute, Korea Hydro & Nuclear Power Co., Ltd.) ;
  • Lee, E.Y. (Nuclear Environment Technology Institute, Korea Hydro & Nuclear Power Co., Ltd.) ;
  • Lee, Y.M. (Korea Atomic Energy Research Institute) ;
  • Kang, C.H. (Korea Atomic Energy Research Institute) ;
  • Zhou, W. (Monitor Scientific LLC) ;
  • Kozak, M.W. (Monitor Scientific LLC)
  • Published : 2004.03.30


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.


  1. IAEA, ISAM, The International Programme for Improving Long Term Safety Assessment Methodologies for Near Surface Radioactive Waste Disposal Facilities: Objectives, Content and Work Programme. Final Version, International Atomic Energy Agency, Vienna (1997)
  2. Kozak, M. W., 'Decision Analysis for LowLevel Radioactive Waste Disposal Facilities', Radioactive Waste Management and Environmental Restoration, 18, 209-223(1994)
  3. SKI, SITE-94: Deep Repository Performance Assessment Project, Swedish Nuclear Power Inspectorate, SKI Report 96:36. Vol. I(1996)
  4. Electric Power Research Institute, Yucca Mountain Total System Performance Assessment, Phase 3, EPRI-TR-107191(1996)
  5. Kozak, M. W., N. E. Olague, R. R. Rao, and J. T. McCord , Evaluation of a Performance Assessment Methodology for Low-Level Radioactive Waste, Volume 1: Evaluation of Modeling Approaches, NUREG/CR-5927 Vol.1, SAND91-2802/1, Sandia National Laboratories(1993)
  6. IAEA, Vault Safety Case Data for the Liquid Release Calculations for the Design Scenario, ISAM Vault Safety Working Group, International Atomic Energy Agency, Vienna (2001)
  7. Kelly E., C. L. Kim, P. Lietava, R. Little, and I. Simon, Safety Assessment of a Vault-based Disposal Facility Using the ISAM Methodology, International Conference on Issues and Trends in RW Management, IAEA, Vienna, Dec.(2002 submitted)