Category of Content
Siting Experience Documents Only
Publication Date
Subject Matter
Neutron Absorber Material Corrosion Testing Final Report
Neutron Absorber Material Corrosion Testing Final Report
Thermodynamic Database for Generic Disposal System Assessment
Thermodynamic Database for Generic Disposal System Assessment
Modeling Coupled THM Processes and Brine Migration in Salt at High Temperatures
Modeling Coupled THM Processes and Brine Migration in Salt at High Temperatures
Thermo-Hydrological and Chemical (THC) Modeling to Support Field Test Design
Thermo-Hydrological and Chemical (THC) Modeling to Support Field Test Design
Neutron Absorber Material Corrosion Testing Preliminary Report
Neutron Absorber Material Corrosion Testing Preliminary Report
Natural system evaluation FY11 year-end report
Natural system evaluation FY11 year-end report
Experimental and Modeling Investigation of Radionuclide Interaction and Transport in Representative Geologic Media
Experimental and Modeling Investigation of Radionuclide Interaction and Transport in Representative Geologic Media
Coupled Thermal-Hydrological-Mechanical Processes in Salt
Coupled Thermal-Hydrological-Mechanical Processes in Salt
Advances in 3D Geologic Modeling of Alluvial Basins with a Focus on Facies and Property Modeling
Advances in 3D Geologic Modeling of Alluvial Basins with a Focus on Facies and Property Modeling
Thermodynamic Properties of Brines, Minerals and Corrosion Products
Thermodynamic Properties of Brines, Minerals and Corrosion Products
Using Environmental Tracers to Estimate Fracture Network Properties
Using Environmental Tracers to Estimate Fracture Network Properties
Neutron Absorber Material Corrosion Testing Final Report FY2021
Neutron Absorber Material Corrosion Testing Final Report FY2021
Support Clad and Neutron Poison Testing
Support Clad and Neutron Poison Testing
THERMODYNAMIC DATABASE DEVELOPMENT, WITH EMPHASIS ON COMPLEX CLAY MINERALS
THERMODYNAMIC DATABASE DEVELOPMENT, WITH EMPHASIS ON COMPLEX CLAY MINERALS
THM Coupled Process Modeling with TOUGH-FLAC to Evaluate the Fate and Transport of Water in
THM Coupled Process Modeling with TOUGH-FLAC to Evaluate the Fate and Transport of Water in
LANL Activities in Model Benchmarking and Thermal Test Design Calculations
LANL Activities in Model Benchmarking and Thermal Test Design Calculations
Advanced Parameter Uncertainty Quantification Using Null Space Latin Hypercube Sampling: Application to Uranium and Neptunium Transport Experiments
Advanced Parameter Uncertainty Quantification Using Null Space Latin Hypercube Sampling: Application to Uranium and Neptunium Transport Experiments
The Effect of Boron on the Thermal Sensitization of Grade A Type
The Effect of Boron on the Thermal Sensitization of Grade A Type
Evaluation of Neutron Absorbers in the DOE Standardized SNF Canister
Evaluation of Neutron Absorbers in the DOE Standardized SNF Canister
DESIGNING A CONSENT-BASED SITING PROCESS: SUMMARY OF PUBLIC INPUT REPORT. Final Draft
DESIGNING A CONSENT-BASED SITING PROCESS: SUMMARY OF PUBLIC INPUT REPORT. Final Draft
Materials for Consideration in Standardized Canister Design Activities??
Materials for Consideration in Standardized Canister Design Activities??
M3SF-19OR0204050160- Criticality Process, Modeling and Status for UNF-STDARDS
M3SF-19OR0204050160- Criticality Process, Modeling and Status for UNF-STDARDS
United Nations Declaration on the Rights of Indigenous Peoples
United Nations Declaration on the Rights of Indigenous Peoples
The General Assembly, Taking note of the recommendation of the Human Rights Council contained in its resolution 1/2 of 29 June 20061 , by which the Council adopted the text of the United Nations Declaration on the Rights of Indigenous Peoples, Recalling its resolution 61/178 of 20 December 2006, by which it decided to defer consideration of and action on the Declaration to allow time for further consultations thereon, and also decided to conclude its consideration before the end of the sixty-first session of the General Assembly, 1 See Official Records of the General Assembly, Sixty-first S
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.