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Summary of Initial Test Results for Transport Properties of Run-of-Mine Salt Backfill
Summary of Initial Test Results for Transport Properties of Run-of-Mine Salt Backfill
Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters
Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters
Np(V) Sorption and Diffusion on Montmorillonite Clay Progress Report
Np(V) Sorption and Diffusion on Montmorillonite Clay Progress Report
Status of International Collaborations on Modeling the BRIE Experiment
Status of International Collaborations on Modeling the BRIE Experiment
Experimental Investigation of Two-Phase Flow in Consolidating and Intact Salt: Analysis of Capillary Pressure Measurements from Core Labs
Experimental Investigation of Two-Phase Flow in Consolidating and Intact Salt: Analysis of Capillary Pressure Measurements from Core Labs
Solubility and Oxidation-State Distribution of Multivalent Actinides in Brines at Elevated Temperatures?
Solubility and Oxidation-State Distribution of Multivalent Actinides in Brines at Elevated Temperatures?
FY20 STATUS REPORT- SNF INTERIM STORAGE CANISTER CORROSION AND SURFACE ENVIRONMENT INVESTIGATIONS
FY20 STATUS REPORT- SNF INTERIM STORAGE CANISTER CORROSION AND SURFACE ENVIRONMENT INVESTIGATIONS
Update to the Salt R&D Reference Case
Update to the Salt R&D Reference Case
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
ADVANCED NUCLEAR FUEL CYCLE EFFECTS ON THE TREATMENT OF UNCERTAINTY IN THE LONG-TERM ASSESSMENT OF GEOLOGIC DISPOSAL SYSTEMS – NATURAL SYSTEM INPUT
ADVANCED NUCLEAR FUEL CYCLE EFFECTS ON THE TREATMENT OF UNCERTAINTY IN THE LONG-TERM ASSESSMENT OF GEOLOGIC DISPOSAL SYSTEMS – NATURAL SYSTEM INPUT
Brine Availability Test in Salt (BATS) FY21 Update
Brine Availability Test in Salt (BATS) FY21 Update
Brine Availability Test in Salt (BATS) Extended Plan for Experiments at the Waste Isolation Pilot Plant
Brine Availability Test in Salt (BATS) Extended Plan for Experiments at the Waste Isolation Pilot Plant
Summary of FY15 Results of Benchmark Modeling Activities
Summary of FY15 Results of Benchmark Modeling Activities
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
Preliminary Test Design and Plan for a Canister Deposition Field Demonstration
Preliminary Test Design and Plan for a Canister Deposition Field Demonstration
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
Mothers for Nuclear Flyer
Mothers for Nuclear Flyer
Mothers for Nuclear Informational Flyer
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.
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.