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Effects of Integral Burnable Absorbers on PWR Spent Nuclear Fuel
Effects of Integral Burnable Absorbers on PWR Spent Nuclear Fuel
Spent Fuel Burnup Credit in Casks: An NRC Perspective
Spent Fuel Burnup Credit in Casks: An NRC Perspective
Until now, the Nuclear Regulatory Commission's (NRC) approval of criticality safety evaluations for spent fuel in transport and storage casks has been based on analyzing the fuel as though it were fresh and without burnable poisons. The well-known nuclide composition of fresh fuel has provided a straightforward and bounding approach for showing that spent fuel systems will remain subcritical under normal and accident conditions. Burnup credit refers to the approval of criticality safety evaluations that consider the decrease in fuel reactivity caused by. irradiation in the reactor.
Selection of Reactor Criticals as Benchmarks for Spent Nuclear Fuels
Selection of Reactor Criticals as Benchmarks for Spent Nuclear Fuels
An Empirical Approach to Bounding the Axial Reactivity Effects of PWR Spent Nuclear Fuel
An Empirical Approach to Bounding the Axial Reactivity Effects of PWR Spent Nuclear Fuel
One of the significant issues yet to be resolved for using
burnup credit ~BUC! for spent nuclear fuel ~SNF! is establishing
a set of depletion parameters that produce an adequately conservative
representation of the fuel’s isotopic inventory. Depletion
parameters ~such as local power, fuel temperature, moderator temperature,
burnable poison rod history, and soluble boron concentration!
affect the isotopic inventory of fuel that is depleted in a
pressurized water reactor ~PWR!. However, obtaining the detailed
Nondestructive Assay of Nuclear Low-Enriched Uranium Spent Fuels for Burnup Credit Application
Nondestructive Assay of Nuclear Low-Enriched Uranium Spent Fuels for Burnup Credit Application
Criticality safety analysis devoted to spent-fuel storage and transportation has to be conservative in order to be sure no accident will ever happen. In the spent-fuel storage field, the assumption of freshness has been used to achieve the conservative aspect of criticality safety procedures. Nevertheless, after being irradiated in a reactor core, the fuel elements have obviously lost part of their original reactivity. The concept of taking into account this reactivity loss in criticality safety analysis is known as burnup credit.
Computational Benchmark of SAS2D Against Spent Fuel Samples from the Takahama-3 Reactor
Computational Benchmark of SAS2D Against Spent Fuel Samples from the Takahama-3 Reactor
Investigation of the Effect of Fixed Absorbers on the Reactivity of PWR Spent Nuclear Fuel for Burnup Credit
Investigation of the Effect of Fixed Absorbers on the Reactivity of PWR Spent Nuclear Fuel for Burnup Credit
The effect of fixed absorbers on the reactivity of pressurized water reactor (PWR) spent nuclear fuel (SNF) in support of burnup-credit criticality safety analyses is examined. A fuel assembly burned in conjunction with fixed absorbers may have a higher reactivity for a given burnup than an assembly that has not used fixed absorbers. As a result, guidance on burnup credit, issued by the U.S. Nuclear Regulatory Commission's Spent Fuel Project Office, recommends restricting the use of burnup credit to assemblies that have not used burnable absorbers.
Effects of the Presence of Axial Blankets and Integral Burnable Absorbers on the End Effect of PWR Burnup Profiles
Effects of the Presence of Axial Blankets and Integral Burnable Absorbers on the End Effect of PWR Burnup Profiles
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
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
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
Research to Support Expansion of U.S. Regulatory Position on Burnup Credit for Transport and Storage Casks
Research to Support Expansion of U.S. Regulatory Position on Burnup Credit for Transport and Storage Casks
In 1999, the United States Nuclear Regulatory Commission (U.S. NRC) initiated a research program
to support the development of technical bases and guidance that would facilitate the implementation of burnup
credit into licensing activities for transport and dry cask storage. This paper reviews the following major areas of
investigation: (1) specification of axial burnup profiles, (2) assumption on cooling time, (3) allowance for
assemblies with fixed and removable neutron absorbers, (4) the need for a burnup margin for fuel with initial