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Siting Experience Documents Only
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Dual-Purpose Canister Filling Demonstration Project Progress Report
Dual-Purpose Canister Filling Demonstration Project Progress 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
Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters
Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters
Public Preferences Related to Consent-Based Siting of Radioactive Waste Management Facilities for Storage and Disposal: Analyzing Variations over Time, Events, and Program Designs ?
Public Preferences Related to Consent-Based Siting of Radioactive Waste Management Facilities for Storage and Disposal: Analyzing Variations over Time, Events, and Program Designs ?
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
Public Views about Storage and Disposal Options for Spent Nuclear Fuel. Energy and Environment Survey, 2017
Public Views about Storage and Disposal Options for Spent Nuclear Fuel. Energy and Environment Survey, 2017
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
Intergenerational Ethical Issues and Communication Related to High-Level Nuclear Waste Repositories
Intergenerational Ethical Issues and Communication Related to High-Level Nuclear Waste Repositories
Purpose of Review: The nuclear power industry started in the 1950s and has now reached a phase of disposing high-level nuclear waste. Since the 1980s, the United Nations has developed a concept of sustainable development and governments have accordingly made ethical commitments to take responsibility towards future generations. The purpose of this review is to examine ethical dilemmas related to high-level nuclear waste disposal in a long-term perspective including potential access to the waste in the future.
Science based responses to social myths on nuclear energy
Science based responses to social myths on nuclear energy
In order to promote a sound basis for considering the role of nuclear in climate change, this review spans the technical topics of social and political debate surrounding nuclear energy with a focus on the objective science of these issues including nuclear waste, accidents and overall risk. Novel aspects include the emergence of nuclear energy as being potentially renewable and the antithesis of Fukushima being an argument for the unacceptable risks associated with the use of nuclear energy.