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FY19 Status Report- SNL Research into Stress Corrosion Cracking of SNF Dry Storage Canisters
FY19 Status Report- SNL Research into Stress Corrosion Cracking of SNF Dry Storage Canisters
Effects of Residual Water on Storage Canister Internal Components
Effects of Residual Water on Storage Canister Internal Components
Status of Progress Made Toward Preliminary Design Concepts for the Inventory in Select Media for DOE-Managed HLW/SNF
Status of Progress Made Toward Preliminary Design Concepts for the Inventory in Select Media for DOE-Managed HLW/SNF
Addressing Facility Needs for Concrete Assessment Using Ultrasonic Testing: Mid-year Report
Addressing Facility Needs for Concrete Assessment Using Ultrasonic Testing: Mid-year Report
Argillite Disposal RD and Argillite International Collaborations - LANL
Argillite Disposal RD and Argillite International Collaborations - LANL
Proposed Waste Management Metrics for the 2013 Evaluation and Screening of Fuel Cycle Options
Proposed Waste Management Metrics for the 2013 Evaluation and Screening of Fuel Cycle Options
Radiolysis Model Sensitivity Analysis for a Used Fuel Storage Canister?
Radiolysis Model Sensitivity Analysis for a Used Fuel Storage Canister?
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Kivetty Site Report
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Kivetty Site Report
Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Hastholmen in Loviisa, Kivetty in Aanekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Kivetty.
Implementation of Small Diameter Borehole Thermal Experiments at WIPP
Implementation of Small Diameter Borehole Thermal Experiments at WIPP
Fuel Cycle Potential Waste Inventory for Disposition
Fuel Cycle Potential Waste Inventory for Disposition
Dual Purpose Canister Reactivity and Groundwater Absorption Analyses
Dual Purpose Canister Reactivity and Groundwater Absorption Analyses
ENSA/DOE TRANSPORT SHOCK AND VIBRATION TEST PLAN
ENSA/DOE TRANSPORT SHOCK AND VIBRATION TEST PLAN
30 cm Drop Tests
30 cm Drop Tests
Mechanical Loads on Spent Nuclear Fuel in the General 30 cm Package Drop Scenario
Mechanical Loads on Spent Nuclear Fuel in the General 30 cm Package Drop Scenario
Update on Gas Sample Collection or CISCC Test Platform Activities
Update on Gas Sample Collection or CISCC Test Platform Activities
Used Nuclear Fuel Characteristics at End of Life
Used Nuclear Fuel Characteristics at End of Life
Disposal Systems Evaluation Framework DSEF Version 2.1 User's Manual
Disposal Systems Evaluation Framework DSEF Version 2.1 User's Manual
Advances in Geologic Disposal System Modeling and Shale Reference Cases
Advances in Geologic Disposal System Modeling and Shale Reference Cases
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Olkiluoto Site Report
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Olkiluoto Site Report
Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Hastholmen in Loviisa, Kivetty in Aanekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Olkiluoto.