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Completion of SRNL Milestone M4FT-12SR0805071, SRNL Support
Completion of SRNL Milestone M4FT-12SR0805071, SRNL Support
Research, Development, and Demonstration Roadmap for Deep Borehole Disposal
Research, Development, and Demonstration Roadmap for Deep Borehole Disposal
DISPOSAL SYSTEMS EVALUATION FRAMEWORK DSEF VERSION 3.0 USER MANUAL
DISPOSAL SYSTEMS EVALUATION FRAMEWORK DSEF VERSION 3.0 USER MANUAL
Evaluation of Used Nuclear Fuel Disposition in Clay-bearing Rocks
Evaluation of Used Nuclear Fuel Disposition in Clay-bearing Rocks
Spent-Fuel Test - Climax: An Evaluation of the Technical Feasibility of Geologic Storage of Spent Nuclear Fuel in Granite
Spent-Fuel Test - Climax: An Evaluation of the Technical Feasibility of Geologic Storage of Spent Nuclear Fuel in Granite
This summary volume outlines results that are covered in more detail in the final report of the Spent-Fuel Test-Climax project. The project was conducted between 1978 and 1983 in the granite Climax stock at the Nevada Test Site. Results indicate that spent fuel can be safely stored for periods of years in this host medium and that nuclear waste so emplaced can be safely retrieved. We also evaluated the effects of heat and radiation (alone and in combination) on emplacement canisters and the surrounding rock mass.
SUPCRTNE Thermodynamic Database Engine
SUPCRTNE Thermodynamic Database Engine
THERMAL MODELING OF A LOADED MAGNASTOR STORAGE SYSTEM AT CATAWBA NUCLEAR STATION
THERMAL MODELING OF A LOADED MAGNASTOR STORAGE SYSTEM AT CATAWBA NUCLEAR STATION
Investigations of Dual-Purpose Canister Direct Disposal Feasibility (FY14)
Investigations of Dual-Purpose Canister Direct Disposal Feasibility (FY14)
State of Knowledge for Colloid Facilitated Radionuclide Transport and Update on Actinide Diffusion in Bentonite Backfill
State of Knowledge for Colloid Facilitated Radionuclide Transport and Update on Actinide Diffusion in Bentonite Backfill
Chloride/Bromide System Radiolysis Model for Integration with the Mixed Potential Model
Chloride/Bromide System Radiolysis Model for Integration with the Mixed Potential Model
Status of International Collaborations on Modeling the BRIE Experiment
Status of International Collaborations on Modeling the BRIE Experiment
Update on Validation and Incorporation of a New Steel Corrosion Module into Fuel Matrix Degradation Model
Update on Validation and Incorporation of a New Steel Corrosion Module into Fuel Matrix Degradation Model
Experiments and Modeling to Support Field Test Design
Experiments and Modeling to Support Field Test Design
Verification and Validation Strategy for Implementation of Hybrid Potts-Phase Field Hydride Modeling Capability in MBM
Verification and Validation Strategy for Implementation of Hybrid Potts-Phase Field Hydride Modeling Capability in MBM
Report on the Status of the UFD Campaign International Activities in Disposal Research at SNL
Report on the Status of the UFD Campaign International Activities in Disposal Research at SNL
SALT REPOSITORY PROJECT CLOSEOUT STATUS REPORT
SALT REPOSITORY PROJECT CLOSEOUT STATUS REPORT
This report provides an overview of the scope and status of the U.S. Department of Energy's (DOE's) Salt Repository Project (SRP) at the time when the project was terminated by the Nuclear Waste Policy Amendments Act of 1987. The report can be used as a "roadmap" into the 10-year program of siting a geologic repository for high-level nuclear waste in rock salt formations. Its purpose is to aid persons interested in the information developed during the course of this effort.