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Siting Experience Documents Only
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Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel
Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel
Degradation Evaluation and Aging Management of Bolted Closure Joints?
Degradation Evaluation and Aging Management of Bolted Closure Joints?
Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel
Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel
Potential Research and Development Opportunities for Light Water Reactor Spent Nuclear Fuel at INL
Potential Research and Development Opportunities for Light Water Reactor Spent Nuclear Fuel at INL
Irradiation and Test Plan for Polymeric Materials
Irradiation and Test Plan for Polymeric Materials
Potential Dual Purpose Canister (DPC) Filler Materials
Potential Dual Purpose Canister (DPC) Filler Materials
Summary of Progress- Modeling Compressible Flow in Microchannels
Summary of Progress- Modeling Compressible Flow in Microchannels
Report documenting prioritized list of UNF assemblies and casks to be modeled
Report documenting prioritized list of UNF assemblies and casks to be modeled
Potential Dual-Purpose Canister (DPC) Filler Materials
Potential Dual-Purpose Canister (DPC) Filler Materials
Corrosion-Resistant Coatings for Mitigation and Repair of Spent Nuclear Fuel Dry Storage Canisters
Corrosion-Resistant Coatings for Mitigation and Repair of Spent Nuclear Fuel Dry Storage Canisters
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
EPRI/DOE High Burnup Fuel Sister Pin Test Plan Simplification and Visualization
EPRI/DOE High Burnup Fuel Sister Pin Test Plan Simplification and Visualization
Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel, Rev. 1
Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel, Rev. 1
Preliminary Report Degradation Evaluation and Aging Management of Bolted Closure Joints?
Preliminary Report Degradation Evaluation and Aging Management of Bolted Closure Joints?
EPRI/DOE High-Burnup Fuel Sister Rod Test Plan Simplification and Visualization
EPRI/DOE High-Burnup Fuel Sister Rod Test Plan Simplification and Visualization
Component Concepts for Advanced Dry Storage Investigations
Component Concepts for Advanced Dry Storage Investigations
Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel
Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel
Technical Work Plan: Environmental Degradation of Materials Relevant to Interim Storage and Permanent Disposal of Used Nuclear Fuel
Technical Work Plan: Environmental Degradation of Materials Relevant to Interim Storage and Permanent Disposal of Used Nuclear Fuel
Task Order 12 Standardized Transportation, Aging an
Task Order 12 Standardized Transportation, Aging an
Materials for Consideration in Standardized Canister Design Activities??
Materials for Consideration in Standardized Canister Design Activities??
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.
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.
Fostering stakeholder involvement across generations - participation after site selection
Fostering stakeholder involvement across generations - participation after site selection
In October 2022, the NEA Forum on Stakeholder Confidence (FSC) organised, in collaboration with the Belgian Agency for Radioactive Waste and Enriched Fissile Materials (ONDRAF/NIRAS), a national workshop in Dessel, Belgium, to explore the topic of stakeholder involvement across generations.
Building on previous work on this topic, participants gathered to discuss how to keep local communities involved in radioactive waste management after site selection, how to engage youth as key stakeholders and which approaches can be used to communicate with stakeholders now and in the future.