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Decay Heat of Selected DOE-Managed Waste Materials
Decay Heat of Selected DOE-Managed Waste Materials
SNF Modeling and Testing - LANL (FY21)
SNF Modeling and Testing - LANL (FY21)
Contribution to L2 Milestone: SNL Overall Control Account
Contribution to L2 Milestone: SNL Overall Control Account
Preliminary Evaluation of Removing Used Nuclear Fuel From Nine Shutdown Sites
Preliminary Evaluation of Removing Used Nuclear Fuel From Nine Shutdown Sites
Sequestration of radioactive iodine in silver-palladium phases incommercial spent nuclear fuel
Sequestration of radioactive iodine in silver-palladium phases incommercial spent nuclear fuel
Summary of Progress- Modeling Compressible Flow in Microchannels
Summary of Progress- Modeling Compressible Flow in Microchannels
Decay Heat of Selected DOE-Managed Waste Materials
Decay Heat of Selected DOE-Managed Waste Materials
Summary of PNNL Transportation Activities for FY12 to Support the UFD Program?
Summary of PNNL Transportation Activities for FY12 to Support the UFD Program?
A Comprehensive Monte Carlo Sampling Uncertainty Quantification Methodology for Used Nuclear Fuel
A Comprehensive Monte Carlo Sampling Uncertainty Quantification Methodology for Used Nuclear Fuel
Preliminary Report: Effects of Irradiation and Thermal Exposure on Elastomeric Seals for Cask Transportation and Storage
Preliminary Report: Effects of Irradiation and Thermal Exposure on Elastomeric Seals for Cask Transportation and Storage
Baseline Studies for Ring Compression Testing of High-Burnup Fuel Cladding
Baseline Studies for Ring Compression Testing of High-Burnup Fuel Cladding
Categorization of Used Nuclear Fuel
Categorization of Used Nuclear Fuel
Experimental Results for SimFuels
Experimental Results for SimFuels
Status of Progress Made Toward Preliminary Design Concepts for the Inventory in Select Media for DOE-Managed HLW/SNF
Status of Progress Made Toward Preliminary Design Concepts for the Inventory in Select Media for DOE-Managed HLW/SNF
Materials and Dimensional Reference Handbook for the Boiling Water Reactor Dry Cask Simulator
Materials and Dimensional Reference Handbook for the Boiling Water Reactor Dry Cask Simulator
Concepts for Small-Scale Testing of Used Nuclear Fuel
Concepts for Small-Scale Testing of Used Nuclear Fuel
Update on the Thermal Hydraulic Investigations of a Horizontal Dry Cask Simulator
Update on the Thermal Hydraulic Investigations of a Horizontal Dry Cask Simulator
Advanced Concepts for Dry Storage Cask Thermal-Hydraulic Testing
Advanced Concepts for Dry Storage Cask Thermal-Hydraulic Testing
Online Waste Library (OWL) and Waste Forms Characteristics Annual Report
Online Waste Library (OWL) and Waste Forms Characteristics Annual Report
Thermal-Hydraulic Results for the Boiling Water Reactor Dry Cask Simulator
Thermal-Hydraulic Results for the Boiling Water Reactor Dry Cask Simulator
Socio-technical multi-criteria evaluation of long-term spent nuclear fuel management strategies: A framework and method
Socio-technical multi-criteria evaluation of long-term spent nuclear fuel management strategies: A framework and method
In the absence of a federal geologic repository or consolidated, interim storage in the United States, commercial spent fuel will remain stranded at some 75 sites across the country. Currently, these include 18 “orphaned sites” where spent fuel has been left at decommissioned reactor sites.
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.
Topical Analysis of Nuclear Experts' Perceptions of Publics, Nuclear Energy, and Sustainable Futures
Topical Analysis of Nuclear Experts' Perceptions of Publics, Nuclear Energy, and Sustainable Futures
Nuclear energy experts consider commercial power from fission to be a strong contender to help mitigate the increasing effects of climate change, in part due to its low-to-no carbon emissions. Nevertheless, nuclear energy's history, including meltdowns such as Three Mile Island, Chernobyl, and Fukushima, and dumping in sacred Indigenous land such as Yucca Mountain, raises important concerns in public deliberation over nuclear power.