Repository 101: Multiple-barrier geological repository design and isolation strategies for safe disposal of radioactive materials

This introductory chapter provides basic insights and guiding principles for establishing and evaluating the long-term safe isolation of radioactive wastes in geological repositories. The intended audience is new technical researchers and reviewers, interested in understanding how their specific expertise is integrated into a multidiscipline safety assessment. The focus is on deep geological disposal, appropriate for the disposal of spent nuclear fuel (SNF), reprocessed high-level waste (HLW), and long-lived, intermediate level waste (LL/ILW). Many of the principles discussed here, however, equally apply to near-surface disposal of lower activity wastes. Two basic types of processes affecting the long-term safe containment and isolation of radioactive waste in deep geological repositories are examined: (1) delay-and-decay processes and (2) concentration-attenuation processes. The robustness of different types of isolation processes, based on their effectiveness and reliability, are discussed. A “top-down” safety assessment of an integrated, multiple-barrier repository system is vital to identify and prioritize safety-important barriers and processes and to use such safety importance insights to guide an efficient and effective research, development, and design program.

[1]  Ivars Neretnieks,et al.  Diffusion in the rock matrix: An important factor in radionuclide retardation? , 1980 .

[2]  Jan Verstricht,et al.  BELGIAN CONCEPT FOR HLW DISPOSAL: DEVELOPMENT AND DEMONSTRATION , 2000 .

[3]  Eric M. Pierce,et al.  The Accelerated Weathering of a Radioactive Low-Activity Waste Glass under Hydraulically Unsaturated Conditions: Experimental Results from a Pressurized Unsaturated Flow Test , 2006 .

[4]  D. Cui,et al.  The fate of radiolytic oxidants during spent fuel leaching in the presence of dissolved near field hydrogen , 2004 .

[5]  J. W. Roddy,et al.  Physical and decay characteristics of commercial LWR spent fuel , 1985 .

[6]  P. Aagaard,et al.  Thermodynamic and kinetic constraints on reaction rates among minerals and aqueous solutions; I, Theoretical considerations , 1982 .

[7]  Joonhong Ahn Mass transfer and transport of radionuclides in fractured porous rock , 1988 .

[8]  Ivars Neretnieks,et al.  Diffusivities of some constituents in compacted wet bentonite clay and the impact on radionuclide migration in the buffer , 1985 .

[9]  S. Kerisit,et al.  Modeling Interfacial Glass‐Water Reactions: Recent Advances and Current Limitations , 2014 .

[10]  T. Pigford,et al.  Analytical Performance Models for Geologic Repositories , 1982 .

[11]  Mick Apted Robust EBS Design and Source-Term Analysis for the Partially Saturated Yucca Mountain Site , 1994 .

[12]  P. A. Witherspoon,et al.  Geological Challenges in Radioactive Waste Isolation: Fourth Worldwide Review , 2001 .

[13]  D. Langmuir Aqueous Environmental Geochemistry , 1997 .

[14]  David K. Peeler,et al.  Measurement of kinetic rate law parameters on a NaCaAl borosilicate glass for low-activity waste , 1997 .

[15]  W. Tiller,et al.  Kinetic Model of Zeolite Paragenesis in Tuffaceous Sediments , 1981 .

[16]  Neil Chapman,et al.  Principles and standards for the disposal of long-lived radioactive wastes , 2003 .

[17]  Rodney C. Ewing,et al.  Uncertainty underground : Yucca Mountain and the nation's high-level nuclear waste , 2006 .

[18]  Joonhong Ahn,et al.  Relationship among Performance of Geologic Repositories, Canister-Array Configuration, and Radionuclide Mass in Waste , 2002 .

[19]  Robert A. Berner,et al.  Early Diagenesis: A Theoretical Approach , 1980 .