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Limited Burnup Credit for Increased Fuel Enrichments in a Swiss PWR Storage Pool
Limited Burnup Credit for Increased Fuel Enrichments in a Swiss PWR Storage Pool
Research Supporting Implementation of Burnup Credit in Transport and Storage Casks
Research Supporting Implementation of Burnup Credit in Transport and Storage Casks
Comparison of Computational Estimations of Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit
Comparison of Computational Estimations of Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit
Impact of Integral Burnable Absorbers on PWR Burnup Credit Criticality Safety Analyses
Impact of Integral Burnable Absorbers on PWR Burnup Credit Criticality Safety Analyses
Parametric Study of Control Rod Exposure for PWR Burnup Credit Criticality Safety Analyses
Parametric Study of Control Rod Exposure for PWR Burnup Credit Criticality Safety Analyses
Spent Fuel Criticality Benchmark Experiments
Spent Fuel Criticality Benchmark Experiments
The Burn-Up Credit Experimental Programme REBUS
The Burn-Up Credit Experimental Programme REBUS
Addressing the Axial Burnup Distribution in PWR Burnup Credit Criticality Safety
Addressing the Axial Burnup Distribution in PWR Burnup Credit Criticality Safety
Reactivity End-Effects Estimates Using a K Perturbation Model
Reactivity End-Effects Estimates Using a K Perturbation Model
Criticality Safety Evaluation of Fuel Storage Pools in Spain
Criticality Safety Evaluation of Fuel Storage Pools in Spain
A Validated Methodology for Evaluating Burnup Credit in Spent Fuel Casks
A Validated Methodology for Evaluating Burnup Credit in Spent Fuel Casks
Characterization of Spent Fuel Approved Testing Material - ATM-104
Characterization of Spent Fuel Approved Testing Material - ATM-104
Uncertainties in Criticality Analysis Which Affect the Storage and Transportation of LWR Fuel
Uncertainties in Criticality Analysis Which Affect the Storage and Transportation of LWR Fuel
Characterization of Spent Fuel Approved Testing Material - ATM 103
Characterization of Spent Fuel Approved Testing Material - ATM 103
Characterization of Spent Fuel Approved Testing Material
Characterization of Spent Fuel Approved Testing Material
Reactivity and Isotopic Composition of Spent PWR Fuel as a Function of Initial Enrichment, Burnup, and Cooling Time
Reactivity and Isotopic Composition of Spent PWR Fuel as a Function of Initial Enrichment, Burnup, and Cooling Time
Feasibility and Incentives for the Consideration of Spent Fuel Operating Histories in the Criticality Analysis of Spent Fuel Shipping Casks
Feasibility and Incentives for the Consideration of Spent Fuel Operating Histories in the Criticality Analysis of Spent Fuel Shipping Casks
Analyses have been completed that indicate the consideration of spent fuel histories (''burnup credit'') in the design of spent fuel shipping casks is a justifiable concept that would result in cost savings and public risk benefits in the transport of spent nuclear fuel. Since cask capacities could be increased over those of casks without burnup credit, the number of shipments necessary to transport a given amount of fuel could be reduced.
Characterization of LWR Spent Fuel MCC-Approved Testing Material--ATM-101
Characterization of LWR Spent Fuel MCC-Approved Testing Material--ATM-101
Generic Reactivity Equivalence of PWR Fuel in Spent Fuel Storage Racks
Generic Reactivity Equivalence of PWR Fuel in Spent Fuel Storage Racks
Conservative Axial Burnup Distributions for Actinide-Only Burnup Credit
Conservative Axial Burnup Distributions for Actinide-Only Burnup Credit
Recommendations Related to Browns Ferry Fire (NUREG-0050)
Recommendations Related to Browns Ferry Fire (NUREG-0050)
On March 22, 1975, a fire was experienced at the Browns Ferry Nuclear Plant near Decatur, Alabama. The Special Review Group was established by the Executive Director for Operations of the Nuclear Regulatory Commission (NRC) soon after the fire to identify the lessons learned from this event and to make recommendations for the future in the light of these lessons. Unless further developments indicate a need to reconvene the Review Group, its task is considered complete with the publication of this report.
Safety Evaluation for Operation of Browns Ferry, Units 1 and 2, Following the March 22, 1975 Fire (NUREG-0061, Initial Report)
Safety Evaluation for Operation of Browns Ferry, Units 1 and 2, Following the March 22, 1975 Fire (NUREG-0061, Initial Report)
On March 22, 1975, a fire at the Browns Ferry Nuclear Plant caused a shutdown of Units 1 and 2. The facility subsequent to the shutdown was found to have incurred substantial damage to power, control, and instrumentation wiring. All three units are presently in the shutdown condition with the fuel removed from the vessels for Units 1 and 2; the Unit 3 reactor is still under construction with operation for that unit scheduled for early 1976.
Report to Congress on Abnormal Occurrences (NUREG-0090)
Report to Congress on Abnormal Occurrences (NUREG-0090)
Section 208 of the Energy Reorganization Act of 1974, as amended (Public Law 93-438), defines an "abnormal occurrence" (AO) as an unscheduled incident or event that the U.S. Nuclear Regulatory Commission (NRC) determines to be significant from the standpoint of public health or safety. The Federal Reports Elimination and Sunset Act of 1995 (Public Law 104-66) requires that the NRC report AOs to Congress annually.
HTC Experimental Program: Validation and Calculational Analysis
HTC Experimental Program: Validation and Calculational Analysis
In the 1980s a series of the Haut Taux de Combustion (HTC) critical experiments with fuel pins in a water-moderated lattice was conducted at the Apparatus B experimental facility in Valduc (Commissariat à l'Energie Atomique, France) with the support of the Institut de Radioprotection et de Sûreté Nucléaire and AREVA NC. Four series of experiments were designed to assess profit associated with actinide-only burnup credit in the criticality safety evaluation for fuel handling, pool storage, and spent-fuel cask conditions.