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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
Initial Site-Specific De-Inventory Reports
Initial Site-Specific De-Inventory Reports
The US Department of Energy (DOE) is exploring options for developing a large-scale transportation system for the safe transport of spent nuclear fuel (SNF) and high-level radioactive waste to future storage or disposal facilities. This complex, large-scale transportation system will involve coordinated, integrated activities. Interfaces with various transportation and non-transportation activities must be defined, and systems must be developed to ensure successful integration when the system becomes operational.
Spent Nuclear Fuel and Reprocessing Waste Inventory, Revision 9
Spent Nuclear Fuel and Reprocessing Waste Inventory, Revision 9
This report provides information on the inventory of spent nuclear fuel (SNF) in the United States located at Nuclear Power Reactor and Independent Spent Fuel Storage Installation sites, as well as SNF and reprocessing waste located at U.S. Department of Energy sites and other research and development centers as of the end of calendar year 2021.
Summary of Consolidated Interim Storage Advantages and Disadvantages from an Integrated Systems Perspective from Prior Reports and Studies
Summary of Consolidated Interim Storage Advantages and Disadvantages from an Integrated Systems Perspective from Prior Reports and Studies
The question of whether centralized storage of civilian spent nuclear fuel (SNF) should be part of the federal waste management system as an intermediate step before permanent disposal has been debated for more than four decades. Centralized storage facilities were included as a potential component of the U.S. spent fuel management system in the Nuclear Waste Policy Act of 1982 (NWPA), but the NWPA did not identify these facilities as being essential.
Does Consolidated Interim Storage Make Sense in an Integrated Waste Management System?
Does Consolidated Interim Storage Make Sense in an Integrated Waste Management System?
Presentation given at the NEI Used Fuel Management Conference in Savannah, Georgia on May 3, 2017. It discusses advantages and disadvantages of consolidated interim storage as well as highlights recent work related to the economics of consolidated storage.
Development of Rail Accident Rates for SNF Rail Shipments
Development of Rail Accident Rates for SNF Rail Shipments
Presentation and Paper for WM 2017. A key factor in evaluating the safety of rail shipments involving the transport of commercial spent nuclear fuel (SNF) is the development of transportation accident rates that are reflective of the unique characteristics associated with these train operations. Typical rail freight operations may involve consists of a hundred cars or more, which may pass through multiple rail yards for trains to be decoupled and reassembled. In contrast, trains carrying SNF are anticipated to be operated in consists of considerably fewer cars.