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Annual status update for OWL
Annual status update for OWL
USED FUEL TESTING TRANSPORTATION OPTIONS-DRAFT
USED FUEL TESTING TRANSPORTATION OPTIONS-DRAFT
On a Thermodynamic Approach to Material Selection for Service in Aggressive Multi-Component Gaseous and/or Vapor Environments
On a Thermodynamic Approach to Material Selection for Service in Aggressive Multi-Component Gaseous and/or Vapor Environments
Effect of Iron on Radiolytic Hydrogen Peroxide Generation
Effect of Iron on Radiolytic Hydrogen Peroxide Generation
Analysis and Documentation of Site Selection and Characterization Activities
Analysis and Documentation of Site Selection and Characterization Activities
Decay Heat of Selected DOE-Managed Waste Materials
Decay Heat of Selected DOE-Managed Waste Materials
Surface Complexation and Ion Exchange Database Development Phase 1: Clay Minerals
Surface Complexation and Ion Exchange Database Development Phase 1: Clay Minerals
Proceedings of the 3rd US German Workshop on Salt Repository Research, Design, and Operation
Proceedings of the 3rd US German Workshop on Salt Repository Research, Design, and Operation
Modeling Coupled THMC Processes and Brine Migration in Salt at High Temperatures
Modeling Coupled THMC Processes and Brine Migration in Salt at High Temperatures
Transparency and Public Participation in Radioactive Waste Management: RISCOM II Final report
Transparency and Public Participation in Radioactive Waste Management: RISCOM II Final report
Long-term radioactive waste management (RWM) involves large and long-term research and development programmes in essentially all countries with civil nuclear programmes. Such programmes develop through different phases from basic research to more focussed applied research and development (R&D) and finally to the design and siting of proposed solutions. Internationally basic principles for the conduct of these programmes, basic safety principles and guidance on how to comply with them have largely been agreed upon.
Argillite International Collaborations – LANL (FY19)
Argillite International Collaborations – LANL (FY19)
Initial Laboratory Unconfined Compression Uniaxial Stress Test Results on Salt
Initial Laboratory Unconfined Compression Uniaxial Stress Test Results on Salt
Corrosion mechanisms for metal alloy waste forms – experiment and theory
Corrosion mechanisms for metal alloy waste forms – experiment and theory
Sister Rod Nondestructive Examination Final Report
Sister Rod Nondestructive Examination Final Report
Rod Internal Pressure Quantification and Distribution Analysis Using FRAPCON
Rod Internal Pressure Quantification and Distribution Analysis Using FRAPCON
Generic Disposal System Environment Modeling – Fiscal Year 2011 Development of the Clay GDSE Model
Generic Disposal System Environment Modeling – Fiscal Year 2011 Development of the Clay GDSE Model
Engineered Barrier System R&D and International Collaborations – LANL (FY18)
Engineered Barrier System R&D and International Collaborations – LANL (FY18)
End of Year Report on S&T Engineering Analysis Accomplishments
End of Year Report on S&T Engineering Analysis Accomplishments
Granular Salt Summary: Reconsolidation Principles and Applications
Granular Salt Summary: Reconsolidation Principles and Applications
Repository Reference Disposal Concepts and Thermal Load Management Analysis
Repository Reference Disposal Concepts and Thermal Load Management Analysis
Swedish Nuclear Waste Efforts
Swedish Nuclear Waste Efforts
The 1976 Parliamentary election in Sweden resulted in a coalition government which imposed extremely stringent requirements for the waste produced by Swedish nuclear power plants. The industry responded with a crash study, the Nuclear Fuel Safety (KBS) project, with experts drawn from hundreds of universities and related scientific institutions. A year later, the industry presented “a complete scheme for absolutely safe storage of nuclear waste” in engineered facilities located at about 500 m depth in the Swedish granite bedrock (KBS-I).