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M3SF-21SN010304064- Disposal Concepts for a High-Temperature Repository in Shale
M3SF-21SN010304064- Disposal Concepts for a High-Temperature Repository in Shale
Low Level Waste Disposition - Quantity and Inventory?, Rev 2
Low Level Waste Disposition - Quantity and Inventory?, Rev 2
Experimental Investigation of Two-Phase Flow in Rock Salt
Experimental Investigation of Two-Phase Flow in Rock Salt
End-of-Year Status Report on Integrated Canister Design and Evaluation
End-of-Year Status Report on Integrated Canister Design and Evaluation
Modeling Coupled THM Processes and Brine Migration in Salt at High Temperatures
Modeling Coupled THM Processes and Brine Migration in Salt at High Temperatures
Thermal and Deposition Modeling of the Canister Deposition Field Demonstration
Thermal and Deposition Modeling of the Canister Deposition Field Demonstration
UPDATE: STRUCTURAL UNCERTAINTY OF USED NUCLEAR FUEL IN DRY STORAGE CANISTERS
UPDATE: STRUCTURAL UNCERTAINTY OF USED NUCLEAR FUEL IN DRY STORAGE CANISTERS
Post-Inspection Evaluation: Thermal Modeling of HI-STORM 100S-218 Version B Storage Modules at Hope Creek Nuclear Power Station ISFSI
Post-Inspection Evaluation: Thermal Modeling of HI-STORM 100S-218 Version B Storage Modules at Hope Creek Nuclear Power Station ISFSI
DOE SFWST Campaign R&D Roadmap Update
DOE SFWST Campaign R&D Roadmap Update
Consequence Analysis of residual water in a storage canister- preliminary report
Consequence Analysis of residual water in a storage canister- preliminary report
Olkiluoto Site Description
Olkiluoto Site Description
This second version of the Olkiluoto Site Report, produced by the OMTF (Olkiluoto Modelling Task Force), updates the Olkiluoto Site Report 2004 (Posiva 2005) with the data and knowledge obtained up to December 2005.<br/>The main product of the modelling has been to develop a descriptive model of the site (the Site Descriptive Model), i.e. a model describing the geometry, properties of the bedrock and the water and the associated interacting processes and mechanisms.
Colloid-Facilitated Radionuclide Transport: Current State of Knowledge from a Nuclear Waste Repository Risk Assessment Perspective
Colloid-Facilitated Radionuclide Transport: Current State of Knowledge from a Nuclear Waste Repository Risk Assessment Perspective
FY17 Status Report: Research on Stress Corrosion Cracking of SNF Interim Storage Canisters?
FY17 Status Report: Research on Stress Corrosion Cracking of SNF Interim Storage Canisters?
Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel, Rev. 1
Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel, Rev. 1
A Comprehensive Monte Carlo Sampling Uncertainty Quantification Methodology for Used Nuclear Fuel
A Comprehensive Monte Carlo Sampling Uncertainty Quantification Methodology for Used Nuclear Fuel
Geological Distribution of Potentially Suitable Shale in the U.S.: Concepts and Literature
Geological Distribution of Potentially Suitable Shale in the U.S.: Concepts and Literature
GDSA – Geologic Modeling – INL – Web Visualization Applications and Assessment Tools
GDSA – Geologic Modeling – INL – Web Visualization Applications and Assessment Tools
Test Plan for Investigation of Material Interactions in Heated Salt
Test Plan for Investigation of Material Interactions in Heated Salt
ANL_M3SF-21AN010309032- Synthesis, Characterization, and Electrochemical Corrosion of SIMFUEL- Preliminary Results
ANL_M3SF-21AN010309032- Synthesis, Characterization, and Electrochemical Corrosion of SIMFUEL- Preliminary Results
Reinvestigation into Closure Predictions of Room D at the Waste Isolation Pilot Plant
Reinvestigation into Closure Predictions of Room D at the Waste Isolation Pilot Plant
Interim Summary Report of the Safety Case
Interim Summary Report of the Safety Case
The report outlines the current design and safety concept for the planned repository. It summarises the approach used to formulate scenarios for the evolution of the disposal system over time, describes these scenarios and presents the main models and computer codes used to analyse them. It also discusses compliance with Finnish regulatory requirements for long-term safety of a geological repository and gives the main evidence, arguments and analyses that lead to confidence, on the part of Posiva, in the long-term safety of the planned repository