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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
A Statistical Method for Estimating the Net Uncertainty in the Prediction of k Based on Isotopic Uncertainties
A Statistical Method for Estimating the Net Uncertainty in the Prediction of k Based on Isotopic Uncertainties
Validation of SCALE-4 for Burnup Credit Applications
Validation of SCALE-4 for Burnup Credit Applications
In the past, criticality analysis of pressurized water reactor (PWR) fuel stored in racks and casks has assumed that the fuel is fresh with the maximum allowable initial enrichment. If credit is allowed for fuel burnup in the design of casks that are used in the transport of spent light water reactor fuel to a repository, the increase in payload can lead to a significant reduction in the cost of transport and a potential reduction in the risk to the public. A portion of the work has been performed at Oak Ridge National Laboratory (ORNL) in support of the U.S.
PWR Radiochemical Assay Benchmarks Using SAS2H and CASMO
PWR Radiochemical Assay Benchmarks Using SAS2H and CASMO
Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit
Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit
Investigation of Average and Pin-Wise Burnup Modeling of PWR Fuel
Investigation of Average and Pin-Wise Burnup Modeling of PWR Fuel
Fission Product Experiment Program: Validation and Calculational Analysis
Fission Product Experiment Program: Validation and Calculational Analysis
From 1998 to 2004, a series of critical experiments referred to as the fission product (FP) experimental program was performed at the Commissariat à l'Energie Atomique Valduc research facility. The experiments were designed by Institut de Radioprotection et de Sûreté Nucléaire (IRSN) and funded by AREVA NC and IRSN within the French program supporting development of a technical basis for burnup credit validation.