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Neutron Absorber Material Corrosion Testing Preliminary Report
Neutron Absorber Material Corrosion Testing Preliminary Report
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
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?
Update to the Salt R&D Reference Case
Update to the Salt R&D Reference Case
Neutron Absorber Material Corrosion Testing Final Report FY2021
Neutron Absorber Material Corrosion Testing Final Report FY2021
Support Clad and Neutron Poison Testing
Support Clad and Neutron Poison Testing
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
The Effect of Boron on the Thermal Sensitization of Grade A Type
The Effect of Boron on the Thermal Sensitization of Grade A Type
Evaluation of Neutron Absorbers in the DOE Standardized SNF Canister
Evaluation of Neutron Absorbers in the DOE Standardized SNF Canister
Materials for Consideration in Standardized Canister Design Activities??
Materials for Consideration in Standardized Canister Design Activities??
M3SF-19OR0204050160- Criticality Process, Modeling and Status for UNF-STDARDS
M3SF-19OR0204050160- Criticality Process, Modeling and Status for UNF-STDARDS
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.
Environmental Risk Characterization Work Plan Yankee Nuclear Power Station Rowe, Massachusetts
Environmental Risk Characterization Work Plan Yankee Nuclear Power Station Rowe, Massachusetts
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.