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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
Probabilistic External Criticality Evaluation
Probabilistic External Criticality Evaluation
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.
Getting to the Core of the Nuclear Fuel Cycle: From the mining of uranium to the disposal of nuclear waste
Getting to the Core of the Nuclear Fuel Cycle: From the mining of uranium to the disposal of nuclear waste
This brochure shortly describes the various steps of the nuclear fuel cycle by covering areas from mining and milling to disposal of spent fuel and other radioactive waste.
Gateway for Accelerated Innovation in Nuclear (GAIN) Website
Gateway for Accelerated Innovation in Nuclear (GAIN) Website
Website for Gateway for Accelerated Innovation in Nuclear (GAIN).
The mission of the Department of Energy Office of Nuclear Energy (DOE-NE) is to advance nuclear power as a resource capable of meeting the nation's energy, environmental and national security needs by resolving technical, cost, safety, proliferation resistance, and security barriers through research, development and demonstration ﴾RD&D﴿.