Selecting Technologies for ETEC Soil Treatability Study
Abstract not provided.
Publications
How Sandia Will Conduct the Soil Treatability Study
Abstract not provided.
The Treatment of Gas Generation in the Waste Isolation Pilot Plant's Safety Case
Abstract not provided.
Demonstrating Long-term Safety for a HLW Repository in Salt
Abstract not provided.
Geochemical Modeling for the WIPP
Abstract not provided.
The Models for the Colloid Source Term at WIPP
Abstract not provided.
Salt disposal of heat-generating nuclear waste
This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from United States repository development, such as seal system design, coupled process simulation, and application of performance assessment methodology, helps define a clear strategy for a heat-generating nuclear waste repository in salt.
Display Posters for Blue Ribbon Commission Reception
Abstract not provided.
Copy of Interim Storage Environmental Justice and Generational Equity
Abstract not provided.
Module 6: Assembly of a Safety Case
Abstract not provided.
Results 51–60 of 60