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Dry Cask Storage and Transportation Burnup Credit
Dry Cask Storage and Transportation Burnup Credit
NRC Burnup Credit Research Program
NRC Burnup Credit Research Program
The Nuclear Energy Research Initiative Burnup Credit Critical Experiment
The Nuclear Energy Research Initiative Burnup Credit Critical Experiment
Reconciliation of Isotopic Uncertainty Between Assays and Integral Benchmarks
Reconciliation of Isotopic Uncertainty Between Assays and Integral Benchmarks
IAEA TCM 2000: An International Meeting on Burnup Credit Applications
IAEA TCM 2000: An International Meeting on Burnup Credit Applications
Actinide-Only Burnup Credit License Application: the CASTOR X/32 S Cask Modeling Details
Actinide-Only Burnup Credit License Application: the CASTOR X/32 S Cask Modeling Details
Applicability of CRC Benchmark Experiments for Burnup Credit Validation
Applicability of CRC Benchmark Experiments for Burnup Credit Validation
Full Burnup Credit in Transport and Storage Casks--Benefits and Implementation
Full Burnup Credit in Transport and Storage Casks--Benefits and Implementation
Sensitivity Coefficient Generation for a Burnup Credit Cask Model Using TSUNAMI-3D
Sensitivity Coefficient Generation for a Burnup Credit Cask Model Using TSUNAMI-3D
Updated Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-Capacity Cask Designs
Updated Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-Capacity Cask Designs
Current Status and Potential Benefits of Burnup Credit for Spent Fuel Transportation
Current Status and Potential Benefits of Burnup Credit for Spent Fuel Transportation
PWR Burnup Credit Using Both Belts and Suspenders
PWR Burnup Credit Using Both Belts and Suspenders
Status of the Joint French ISPN/COGEMA Qualification Programme of Fission Products
Status of the Joint French ISPN/COGEMA Qualification Programme of Fission Products
Design of Wet Storage Racks for Spent BWR Fuel
Design of Wet Storage Racks for Spent BWR Fuel
SAS2D--A Two-Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel
SAS2D--A Two-Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel
Development and Applications of a Protypic SCALE Control Module for Automated Burnup Credit Analysis
Development and Applications of a Protypic SCALE Control Module for Automated Burnup Credit Analysis
Use Burnup Credit for Criticality Safety for the Hanford Spent Nuclear Fuel Project
Use Burnup Credit for Criticality Safety for the Hanford Spent Nuclear Fuel Project
Impact of Partially Inserted Control Rods on Actinide-Only Burnup Credit Margin
Impact of Partially Inserted Control Rods on Actinide-Only Burnup Credit Margin
A New Method to Take Burnup into Account in Criticality Studies Considering an Axial Profile of Burn-up Plus some Fission Products
A New Method to Take Burnup into Account in Criticality Studies Considering an Axial Profile of Burn-up Plus some Fission Products
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.
Consent-Based Siting Consortia flyer
Consent-Based Siting Consortia flyer
Consent-based siting is an approach that seeks communities’ willing and informed consent to accept new development or host a project in their area. The U.S. Department of Energy (DOE) is using a consent-based siting process to identify one or more federal consolidated interim storage facilities for the nation’s spent nuclear fuel, a byproduct of nuclear power generation. Spent nuclear fuel is currently stored at more than 70 sites across the country in communities that did not agree to host the material long term.
Consent-Based Siting flyer
Consent-Based Siting flyer
What is Consent-Based Siting?
Consent-based siting is an approach that seeks the willing and informed consent of people and communities to host a project in their area. This process is designed to be flexible, adaptive, and responsive to community concerns.
How is DOE using Consent-Based Siting? How can people and communities participate?
Atlas Railcar factsheet
Atlas Railcar factsheet
The U.S. Department of Energy (DOE) is developing special railcars for future large-scale DOE transport of spent nuclear fuel (SNF) from nuclear power plants. Designs include new buffer railcars, the Atlas railcar (to transport SNF containers), and a new escort railcar for security personnel that was developed in collaboration with the U.S. Navy. All railcars are expected to complete testing and meet North American freight safety standards in 2023.
5 Common Myths about Transporting Spent Nuclear Fuel flyer
5 Common Myths about Transporting Spent Nuclear Fuel flyer
Despite being safely transported in the U.S. for more than half a century, many still believe spent nuclear fuel (SNF) is too dangerous to transport. But, in reality, it’s a well-coordinated process with a great track record—and we have the facts to prove it.