Category of Content
Siting Experience Documents Only
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Subject Matter
Thermal Conductivity of Salt as a Function of Porosity
Thermal Conductivity of Salt as a Function of Porosity
Experiments and Modeling in Support of Generic Salt Repository Science
Experiments and Modeling in Support of Generic Salt Repository Science
Generic Natural S ys tem Conceptual Model and Numerical Architecture
Generic Natural S ys tem Conceptual Model and Numerical Architecture
FINAL TEST PLAN FOR FY2013 BRINE MIGRATION EXPERIMENTS
FINAL TEST PLAN FOR FY2013 BRINE MIGRATION EXPERIMENTS
Engineered Barrier System Research Activities at LBNL Via International Collaboration: FY19 Progress Report
Engineered Barrier System Research Activities at LBNL Via International Collaboration: FY19 Progress Report
DISPOSAL SYSTEMS MATERIAL PROPERTIES THERMODYNAMIC DATA COLLECTION AND SYNTHESIS
DISPOSAL SYSTEMS MATERIAL PROPERTIES THERMODYNAMIC DATA COLLECTION AND SYNTHESIS
Analysis of Data From Salt Reconsolidation Experiments at SNL in FY12 and FY13
Analysis of Data From Salt Reconsolidation Experiments at SNL in FY12 and FY13
Investigation of Reactive Transport and Coupled THM Processes in EBS: FY12 Report
Investigation of Reactive Transport and Coupled THM Processes in EBS: FY12 Report
International Collaborations Activities on Disposal in Argillite RD- Bentonite Barrier Characterization
International Collaborations Activities on Disposal in Argillite RD- Bentonite Barrier Characterization
Summary of FY15 Results of Benchmark Modeling Activities
Summary of FY15 Results of Benchmark Modeling Activities
Evaluation of Engineered Barrier Systems in the Disposition of Spent Nuclear Fuel
Evaluation of Engineered Barrier Systems in the Disposition of Spent Nuclear Fuel
Partitioning of Fission Products (Cs, Sr and I) into Salt Phases
Partitioning of Fission Products (Cs, Sr and I) into Salt Phases
Status of LANL investigations of temperature constraints on clay in repository environments
Status of LANL investigations of temperature constraints on clay in repository environments
Multi-pack Disposal Concepts for Spent Fuel
Multi-pack Disposal Concepts for Spent Fuel
A Salt Repository Concept for CSNF in 21-PWR Size Canisters
A Salt Repository Concept for CSNF in 21-PWR Size Canisters
Multi-pack Disposal Concepts for Spent Fuel
Multi-pack Disposal Concepts for Spent Fuel
A Salt Repository Concept for CSNF in 21-PWR Size Canisters, Rev 2
A Salt Repository Concept for CSNF in 21-PWR Size Canisters, Rev 2
Nuclear Power Plant Infrastructure Evaluations for Removal of Spent Nuclear Fuel (2024)
Nuclear Power Plant Infrastructure Evaluations for Removal of Spent Nuclear Fuel (2024)
This report fulfills the M3 milestone M3SF-23PN0203020614, “Updated NPP Site Evaluation Report (2).” This report is an update of the 2021 report Nuclear Power Plant Infrastructure Evaluations for Removal of Spent Nuclear Fuel and includes expansion of the site evaluations to include operating nuclear power plant (NPP) sites and to incorporate updated site inventory data. Figures that include the number of spent nuclear fuel (SNF) assemblies and metric tons heavy metal (MTHM) in a single figure have also been added to the report.
Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel: 2022 Update
Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel: 2022 Update
In October 2009, the U.S. Nuclear Waste Technical Review Board (Board or NWTRB) published Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel. For each of the 13 national programs studied, the report catalogued 15 institutional arrangements that had been set in place and 15 technical approaches that had been taken to design repository systems for the long-term management of high-activity radioactive waste.