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Solubility and Oxidation-State Distribution of Multivalent Actinides in Brines at Elevated Temperatures?
Solubility and Oxidation-State Distribution of Multivalent Actinides in Brines at Elevated Temperatures?
Status of Diffusion-Reaction Modeling of the DR-A Field Experiment at Mont Terri, Switzerland
Status of Diffusion-Reaction Modeling of the DR-A Field Experiment at Mont Terri, Switzerland
Status Report on Radionuclide Solubility Experimental Studies
Status Report on Radionuclide Solubility Experimental Studies
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
Section 180(c) Proposed Policy Implementation Exercise: Lessons Learned?
Section 180(c) Proposed Policy Implementation Exercise: Lessons Learned?
RADTRAN 6/RadCat 6 User Guide, Rev 2
RADTRAN 6/RadCat 6 User Guide, Rev 2
RADTRAN 6 Technical Manual
RADTRAN 6 Technical Manual
Full-Scale Accident Testing in Support of Spent Nuclear Fuel Transportation
Full-Scale Accident Testing in Support of Spent Nuclear Fuel Transportation
Transportation Planning: Indigenous Dialogue
Transportation Planning: Indigenous Dialogue
In 2019, the NWMO commissioned Maawandoon Inc to lead Indigenous Dialogue session to support NWMO’s transportation planning for the long-term care of Canada’s used nuclear fuel. This research built upon and complemented public attitude research carried out in 2017 and 2018. The research methodology consisted of 7 Indigenous dialogue sessions and attendance at 3 Indigenous Annual General Assemblies (AGA)/meetings with dialogue components.
Views and Attitudes toward Nuclear Waste: National Survey Final Report
Views and Attitudes toward Nuclear Waste: National Survey Final Report
In 2002, the federal government passed a law to create the Nuclear Waste Management Organization, also known by its initials NWMO. The Nuclear Waste Management Organization (NWMO) was established by Ontario Power Generation Inc., Hydro-Québec and New Brunswick Power Corporation in accordance with the Nuclear Fuel Waste Act (NFWA) to assume responsibility for the long-term management of Canada’s used nuclear fuel. More specifically, the NWMO’s initial objective was to recommend a long-term approach for managing used nuclear fuel produced by Canada’s electricity generators.