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Feasibility Study of Direct Disposal of Electrorefining (ER) Salt Waste in a Salt Repository: Laboratory Tests
Feasibility Study of Direct Disposal of Electrorefining (ER) Salt Waste in a Salt Repository: Laboratory Tests
Stability of Intrinsic Pu colloids in the Presence of Montmorillonite at 25 and 80°C: High-fired and freshly prepared PuO2 oxide
Stability of Intrinsic Pu colloids in the Presence of Montmorillonite at 25 and 80°C: High-fired and freshly prepared PuO2 oxide
Update to the Salt R&D Reference Case
Update to the Salt R&D Reference Case
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
Thermomechanical-Hydrological and Chemical (TMHC) Model Development
Thermomechanical-Hydrological and Chemical (TMHC) Model Development
ADVANCED NUCLEAR FUEL CYCLE EFFECTS ON THE TREATMENT OF UNCERTAINTY IN THE LONG-TERM ASSESSMENT OF GEOLOGIC DISPOSAL SYSTEMS – NATURAL SYSTEM INPUT
ADVANCED NUCLEAR FUEL CYCLE EFFECTS ON THE TREATMENT OF UNCERTAINTY IN THE LONG-TERM ASSESSMENT OF GEOLOGIC DISPOSAL SYSTEMS – NATURAL SYSTEM INPUT
Preliminary Interpretation of a Radionuclide and Colloid Tracer Test in a Granodiorite Shear Zone at the Grimsel Test Site, Switzerland
Preliminary Interpretation of a Radionuclide and Colloid Tracer Test in a Granodiorite Shear Zone at the Grimsel Test Site, Switzerland
Brine Availability Test in Salt (BATS) FY21 Update
Brine Availability Test in Salt (BATS) FY21 Update
Partitioning of Fission Products (Cs, Sr and I) into Salt Phases
Partitioning of Fission Products (Cs, Sr and I) into Salt Phases
Brine Availability Test in Salt (BATS) Extended Plan for Experiments at the Waste Isolation Pilot Plant
Brine Availability Test in Salt (BATS) Extended Plan for Experiments at the Waste Isolation Pilot Plant
Summary of FY15 Results of Benchmark Modeling Activities
Summary of FY15 Results of Benchmark Modeling Activities
Partitioning of Fission Products (Cs, Sr and I) into Salt Phases
Partitioning of Fission Products (Cs, Sr and I) into Salt Phases
Laboratory Experiments on Bentonite Samples: FY15 Progress (S&T Accomplishment Report)
Laboratory Experiments on Bentonite Samples: FY15 Progress (S&T Accomplishment Report)
Modeling Radionuclide Transport in Clays
Modeling Radionuclide Transport in Clays
Diffusion Modeling in a Generic Clay Repository: Impacts of Heterogeneity and Electro-Chemical Process
Diffusion Modeling in a Generic Clay Repository: Impacts of Heterogeneity and Electro-Chemical Process
Radiolytic Specie Generation from Internal Waste Package Criticality
Radiolytic Specie Generation from Internal Waste Package Criticality
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.
Getting to the Core of the Nuclear Fuel Cycle: From the mining of uranium to the disposal of nuclear waste
Getting to the Core of the Nuclear Fuel Cycle: From the mining of uranium to the disposal of nuclear waste
This brochure shortly describes the various steps of the nuclear fuel cycle by covering areas from mining and milling to disposal of spent fuel and other radioactive waste.
Gateway for Accelerated Innovation in Nuclear (GAIN) Website
Gateway for Accelerated Innovation in Nuclear (GAIN) Website
Website for Gateway for Accelerated Innovation in Nuclear (GAIN).
The mission of the Department of Energy Office of Nuclear Energy (DOE-NE) is to advance nuclear power as a resource capable of meeting the nation's energy, environmental and national security needs by resolving technical, cost, safety, proliferation resistance, and security barriers through research, development and demonstration ﴾RD&D﴿.