The application of burnup credit requires calculating the isotopic inventory of the irradiated fuel. The depletion calculation simulates the burnup of the fuel under reactor operating conditions. The result of the depletion analysis is the predicted isotopic composition, which is ultimately input to a criticality analysis to determine the system multiplication factor (k{sub eff}). This paper demonstrates an approach for calculating the isotopic bias and uncertainty in k{sub eff} for commercial spent nuclear fuel burnup credit. This paper covers 74 different radiochemical assayed spent fuel samples from 22 different fuel assemblies that were irradiated in eight different pressurized water reactors (PWRs). The samples evaluated span an enrich...
In the past, criticality safety analyses for spent fuel storage and transport canisters assumed the ...
We present a summary of the actinide-plus-fission-product burnup credit criticality safety licensing...
The Topical Report on Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel P...
The primary purpose of this paper is to present the new methodology for establishing bias and uncert...
Burnup credit methodology is economically advantageous because significantly higher loading capacity...
Safety analyses of criticality control systems for transportation packages include an assumption tha...
This report describes a novel approach developed at the Oak Ridge National Laboratory (ORNL) for the...
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuc...
One of the methodologies used in criticality safety analysis is burnup credit method, which allows c...
One of the methodologies used in criticality safety analysis is burnup credit method, which allows c...
The paper shows the usage of destructive assay data from PWR fuel samples for the validation of the ...
This report is one of the several recent NUREG/CR reports documenting benchmark-quality radiochemica...
Burnup credit is an ongoing technical concern for many countries that operate commercial nuclear pow...
We present a summary of the actinide-plus-fission-product burnup credit criticality safety licensing...
Isotopic characterization of spent fuel via depletion and decay calculations is necessary for determ...
In the past, criticality safety analyses for spent fuel storage and transport canisters assumed the ...
We present a summary of the actinide-plus-fission-product burnup credit criticality safety licensing...
The Topical Report on Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel P...
The primary purpose of this paper is to present the new methodology for establishing bias and uncert...
Burnup credit methodology is economically advantageous because significantly higher loading capacity...
Safety analyses of criticality control systems for transportation packages include an assumption tha...
This report describes a novel approach developed at the Oak Ridge National Laboratory (ORNL) for the...
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuc...
One of the methodologies used in criticality safety analysis is burnup credit method, which allows c...
One of the methodologies used in criticality safety analysis is burnup credit method, which allows c...
The paper shows the usage of destructive assay data from PWR fuel samples for the validation of the ...
This report is one of the several recent NUREG/CR reports documenting benchmark-quality radiochemica...
Burnup credit is an ongoing technical concern for many countries that operate commercial nuclear pow...
We present a summary of the actinide-plus-fission-product burnup credit criticality safety licensing...
Isotopic characterization of spent fuel via depletion and decay calculations is necessary for determ...
In the past, criticality safety analyses for spent fuel storage and transport canisters assumed the ...
We present a summary of the actinide-plus-fission-product burnup credit criticality safety licensing...
The Topical Report on Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel P...