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Dual-Purpose Canister Filling Demonstration Project Progress Report
Dual-Purpose Canister Filling Demonstration Project Progress Report
Electrochemical Experiments Supporting the ANL Oxide Fuel Corrosion Model
Electrochemical Experiments Supporting the ANL Oxide Fuel Corrosion Model
Dual-Purpose Canister Filling Demonstration Project Progress Report
Dual-Purpose Canister Filling Demonstration Project Progress Report
FY12 Sensitivity Studies Using the UFD Clay Generic Disposal System Model
FY12 Sensitivity Studies Using the UFD Clay Generic Disposal System Model
Dual-Purpose Canister Filling Demonstration Project Progress Report
Dual-Purpose Canister Filling Demonstration Project Progress Report
Modeling and Analysis to Support Spent Nuclear Fuel Drop Tests
Modeling and Analysis to Support Spent Nuclear Fuel Drop Tests
Used Fuel Degradation and Radionuclide Mobilization: Experimental Plan for Electrochemical Corrosion Studies
Used Fuel Degradation and Radionuclide Mobilization: Experimental Plan for Electrochemical Corrosion Studies
Report on In-situ and Electrochemical Work for Model Validation
Report on In-situ and Electrochemical Work for Model Validation
Modeling and Analysis for Spent Nuclear Fuel Seismic Testing
Modeling and Analysis for Spent Nuclear Fuel Seismic Testing
In-Situ Electrochemical Testing of Uranium Oxide Alteration under Anoxic Conditions
In-Situ Electrochemical Testing of Uranium Oxide Alteration under Anoxic Conditions
Partitioning of Fission Products (Cs, Sr and I) into Salt Phases
Partitioning of Fission Products (Cs, Sr and I) into Salt Phases
Mixed Potential Model for Used Fuel Dissolution - Fortran Code
Mixed Potential Model for Used Fuel Dissolution - Fortran Code
Waste Form Degradation Model Status Report: Electrochemical Model for Used Fuel Matrix Degradation Rate
Waste Form Degradation Model Status Report: Electrochemical Model for Used Fuel Matrix Degradation Rate
Addition of Bromide to Radiolysis Model Formulation for Integration with the Mixed Potential Model
Addition of Bromide to Radiolysis Model Formulation for Integration with the Mixed Potential Model
Spent Fuel Matrix Spent Fuel Matrix Degradation and Canister Corrosion: Quantifying the Effect of Hydrogen on Radionuclide Source Term
Spent Fuel Matrix Spent Fuel Matrix Degradation and Canister Corrosion: Quantifying the Effect of Hydrogen on Radionuclide Source Term
In-Situ Electrochemical Testing of Uranium Oxide Alteration under Anoxic Conditions
In-Situ Electrochemical Testing of Uranium Oxide Alteration under Anoxic Conditions
Mixed Potential Model for Used Fuel Dissolution - Fortran Code
Mixed Potential Model for Used Fuel Dissolution - Fortran Code
Dual-Purpose Canister Filling Demonstration Project Progress Report
Dual-Purpose Canister Filling Demonstration Project Progress Report
Waste Form Degradation and Radionuclide Mobilization: Progress Report
Waste Form Degradation and Radionuclide Mobilization: Progress Report
Materials for Consideration in Standardized Canister Design Activities??
Materials for Consideration in Standardized Canister Design Activities??
Interim Storage, Environmental Justice, and Generational Equity
Interim Storage, Environmental Justice, and Generational Equity
With the termination of the Yucca Mountain project, which was proposed to be our nation’s first repository for the disposal of military and civilian spent nuclear fuel and high-level radioactive waste, the future of nuclear waste management and disposal in this country became increasingly uncertain. Interim storage has been advocated by many as a temporary solution while a permanent solution is studied for potentially several more decades to come.
EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages
EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages
Probabilistic External Criticality Evaluation
Probabilistic External Criticality Evaluation
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.