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Cavern/Vault Disposal Concepts and Thermal Calculations for Direct Disposal of 37- PWR Size: DPCs
Cavern/Vault Disposal Concepts and Thermal Calculations for Direct Disposal of 37- PWR Size: DPCs
Summary of Progress- Modeling Compressible Flow in Microchannels
Summary of Progress- Modeling Compressible Flow in Microchannels
Summary of PNNL Transportation Activities for FY12 to Support the UFD Program?
Summary of PNNL Transportation Activities for FY12 to Support the UFD Program?
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
REPOSITORY NEAR-FIELD THERMAL MODELING UPDATE INCLUDING ANALYSIS OF OPEN MODE DESIGN CONCEPTS, Draft Rev M
REPOSITORY NEAR-FIELD THERMAL MODELING UPDATE INCLUDING ANALYSIS OF OPEN MODE DESIGN CONCEPTS, Draft Rev M
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
REPOSITORY NEAR-FIELD THERMAL MODELING UPDATE INCLUDING ANALYSIS OF OPEN MODE DESIGN CONCEPTS
REPOSITORY NEAR-FIELD THERMAL MODELING UPDATE INCLUDING ANALYSIS OF OPEN MODE DESIGN CONCEPTS
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
Thermal-Hydraulic Results for the Boiling Water Reactor Dry Cask Simulator
Thermal-Hydraulic Results for the Boiling Water Reactor Dry Cask Simulator
A Salt Repository Concept for CSNF in 21-PWR Size Canisters
A Salt Repository Concept for CSNF in 21-PWR Size Canisters
A Salt Repository Concept for CSNF in 21-PWR Size Canisters, Rev 2
A Salt Repository Concept for CSNF in 21-PWR Size Canisters, Rev 2
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.
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.