Category of Content
Siting Experience Documents Only
Publication Date
Subject Matter
Country
Keywords
Thermodynamic and Sorption Data FY15 Project Report
Thermodynamic and Sorption Data FY15 Project Report
Potential Dual-Purpose Canister (DPC) Filler Materials
Potential Dual-Purpose Canister (DPC) Filler Materials
The Final Disposal Facility for Spent Nuclear Fuel
The Final Disposal Facility for Spent Nuclear Fuel
Thorough long-term studies have shown that the Finnish bedrock is suitable for the permanent isolation of spent nuclear fuel from organic nature. Legislation requires that besides safety, an assessment be made of any other environmental impacts of the final disposal facility. Environmental impact assessment (EIA) in respect of the final disposal facility for spent nuclear fuel got under way in 1997 when Posiva Oy, which is responsible for the project, began work on an EIA programme.
Summary of Meeting Between DOE and SNL to Discuss the Siting Experience Archive
Summary of Meeting Between DOE and SNL to Discuss the Siting Experience Archive
Ion Selective Ceramics for Waste Separations: Performance and Design of Ion Selective Ceramic Membrane for Molten Salt Recycle
Ion Selective Ceramics for Waste Separations: Performance and Design of Ion Selective Ceramic Membrane for Molten Salt Recycle
Mathematical Basis and Test Cases for Colloid-Facilitated Radionuclide Transport Modeling in GDSA-PFLOTRAN
Mathematical Basis and Test Cases for Colloid-Facilitated Radionuclide Transport Modeling in GDSA-PFLOTRAN
Generic Deep Geologic Disposal Safety Case, Rev 1
Generic Deep Geologic Disposal Safety Case, Rev 1
Crystalline and Crystalline International Disposal Activities
Crystalline and Crystalline International Disposal Activities
Deep Borehole Field Test Specifications
Deep Borehole Field Test Specifications
Decay Heat of Selected DOE-Managed Waste Materials
Decay Heat of Selected DOE-Managed Waste Materials
Technical Feasibility of Measuring Low-Stress, Low Strain-Rate Deformation Relevant to a Salt Repository
Technical Feasibility of Measuring Low-Stress, Low Strain-Rate Deformation Relevant to a Salt Repository
Alternative Concepts for Direct Disposal of Dual-Purpose Canisters
Alternative Concepts for Direct Disposal of Dual-Purpose Canisters
FY18 Progress of EBS International Collaborations
FY18 Progress of EBS International Collaborations
Nuclear Waste Policy Act (Section 112) - Environmental Assessment: Richton Dome Site, Mississippi Volume I
Nuclear Waste Policy Act (Section 112) - Environmental Assessment: Richton Dome Site, Mississippi Volume I
The Nuclear Waste Policy Act of 1982 (the Act) established a process for the selection of sites for the disposal of spent nuclear fuel and high-level radioactive waste in geologic repositories. The first steps in this process were the identification of potentially acceptable sites and the development of general guidelines for siting repositories. In February 1983, the DOE identified nine sites in six States as potentially acceptable for the first repository. The Richton Dome site in Perry County, Mississippi, was identified as one of those sites.
Large Plate Experiment of Chloride-induced Stress Corrosion Cracking in Spent Nuclear Fuel Storage
Large Plate Experiment of Chloride-induced Stress Corrosion Cracking in Spent Nuclear Fuel Storage
A Preliminary Evaluation of Using Fill Materials to Stabilize Used Nuclear Fuel During Storage and Transportation
A Preliminary Evaluation of Using Fill Materials to Stabilize Used Nuclear Fuel During Storage and Transportation
FY 2012 Year-End Status of Standardized Canisters and Feasibility of Direct Disposal of Dual Purpose Canisters
FY 2012 Year-End Status of Standardized Canisters and Feasibility of Direct Disposal of Dual Purpose Canisters
Proceedings of the 5th US German Workshop on Salt Repository Research, Design and Operation.
Proceedings of the 5th US German Workshop on Salt Repository Research, Design and Operation.
Investigation of Cold Spray as a Dry Storage Canister Repair and Mitigation Tool
Investigation of Cold Spray as a Dry Storage Canister Repair and Mitigation Tool
Evaluation of Engineered Barrier Systems FY19 Report
Evaluation of Engineered Barrier Systems FY19 Report
Sensitivity of Spent Fuel Temperatures to Variable Canister Backfills
Sensitivity of Spent Fuel Temperatures to Variable Canister Backfills
Expert Judgement in Performance Assessment
Expert Judgement in Performance Assessment
Proposals to site, construct and operate a radioactive waste disposal facility in Sweden will be supported by performance assessments (PAs). Such PAs will require a range of expert judgements to be made. As part of SKI’s preparation for reviewing SKB’s Pas and for conducting independent PAs, SKI has identified a need for further research on the treatment of expert judgement in PA.