Category of Content
Siting Experience Documents Only
Publication Date
Subject Matter
Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters
Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters
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
FY20 STATUS REPORT- SNF INTERIM STORAGE CANISTER CORROSION AND SURFACE ENVIRONMENT INVESTIGATIONS
FY20 STATUS REPORT- SNF INTERIM STORAGE CANISTER CORROSION AND SURFACE ENVIRONMENT INVESTIGATIONS
Baseline Studies for Ring Compression Testing of High-Burnup Fuel Cladding
Baseline Studies for Ring Compression Testing of High-Burnup Fuel Cladding
Sensitivity of Spent Fuel Temperatures to Variable Canister Backfills
Sensitivity of Spent Fuel Temperatures to Variable Canister Backfills
Analysis of Dust Samples Collected from an In-Service Interim Storage System at the Maine Yankee Nuclear Site
Analysis of Dust Samples Collected from an In-Service Interim Storage System at the Maine Yankee Nuclear Site
Status Update on the Canister Deposition Field Demonstration
Status Update on the Canister Deposition Field Demonstration
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
Update on the Thermal Hydraulic Investigations of a Horizontal Dry Cask Simulator
Update on the Thermal Hydraulic Investigations of a Horizontal Dry Cask Simulator
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
Advanced Concepts for Dry Storage Cask Thermal-Hydraulic Testing
Advanced Concepts for Dry Storage Cask Thermal-Hydraulic Testing
Preliminary Test Design and Plan for a Canister Deposition Field Demonstration
Preliminary Test Design and Plan for a Canister Deposition Field Demonstration
Thermal-Hydraulic Results for the Boiling Water Reactor Dry Cask Simulator
Thermal-Hydraulic Results for the Boiling Water Reactor Dry Cask Simulator
Materials for Consideration in Standardized Canister Design Activities??
Materials for Consideration in Standardized Canister Design Activities??
M3SF-21PN020401053- COBRA-SFS Version 6.1 User Guide- A Thermal Hydraulic Analysis Code for Spent Fuel Storage and Transpor
M3SF-21PN020401053- COBRA-SFS Version 6.1 User Guide- A Thermal Hydraulic Analysis Code for Spent Fuel Storage and Transpor
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.