Isotopic characterization of spent fuel via depletion and decay calculations is necessary for determination of source terms for subsequent system analyses involving heat transfer, radiation shielding, isotopic migration, etc. Unlike fresh fuel assumptions typically employed in the criticality safety analysis of spent fuel configurations, burnup credit applications also rely on depletion and decay calculations to predict the isotopic composition of spent fuel. These isotopics are used in subsequent criticality calculations to assess the reduced worth of spent fuel. To validate the codes and data used in depletion approaches, experimental measurements are compared with numerical predictions for relevant spent fuel samples. Such comparisons ha...
Acquisition and analysis of experimental isotopic assay data are essential for validating computer c...
Six uranium isotopes and fourteen fission product isotopes were calculated on a mass basis at end-of...
The isotopic composition of mixed-oxide fuel (fabricated with both uranium and plutonium isotope) di...
Isotopic characterization of spent fuel via depletion and decay calculations is necessary for determ...
Thirty spent fuel samples obtained from boiling-water-reactor (BWR) fuel pins have been modeled at O...
Thirty spent fuel samples obtained from boiling-water-reactor (BWR) fuel pins have been modeled at O...
Burnup credit methodology is economically advantageous because significantly higher loading capacity...
Safety analyses of criticality control systems for transportation packages include an assumption tha...
The application of burnup credit requires calculating the isotopic inventory of the irradiated fuel....
This report is one of the several recent NUREG/CR reports documenting benchmark-quality radiochemica...
The isotopic composition of mixed-oxide (MOX) fuel, fabricated with both uranium and plutonium, afte...
The paper shows the usage of destructive assay data from PWR fuel samples for the validation of the ...
Burnup credit (BUC) is a concept applied in the criticality safety analysis of spent nuclear fuel in...
This work investigates the depletion capability implemented in lattice physics code STREAM for the p...
The purpose of this calculation report is to document the comparison to measurement of the isotopic ...
Acquisition and analysis of experimental isotopic assay data are essential for validating computer c...
Six uranium isotopes and fourteen fission product isotopes were calculated on a mass basis at end-of...
The isotopic composition of mixed-oxide fuel (fabricated with both uranium and plutonium isotope) di...
Isotopic characterization of spent fuel via depletion and decay calculations is necessary for determ...
Thirty spent fuel samples obtained from boiling-water-reactor (BWR) fuel pins have been modeled at O...
Thirty spent fuel samples obtained from boiling-water-reactor (BWR) fuel pins have been modeled at O...
Burnup credit methodology is economically advantageous because significantly higher loading capacity...
Safety analyses of criticality control systems for transportation packages include an assumption tha...
The application of burnup credit requires calculating the isotopic inventory of the irradiated fuel....
This report is one of the several recent NUREG/CR reports documenting benchmark-quality radiochemica...
The isotopic composition of mixed-oxide (MOX) fuel, fabricated with both uranium and plutonium, afte...
The paper shows the usage of destructive assay data from PWR fuel samples for the validation of the ...
Burnup credit (BUC) is a concept applied in the criticality safety analysis of spent nuclear fuel in...
This work investigates the depletion capability implemented in lattice physics code STREAM for the p...
The purpose of this calculation report is to document the comparison to measurement of the isotopic ...
Acquisition and analysis of experimental isotopic assay data are essential for validating computer c...
Six uranium isotopes and fourteen fission product isotopes were calculated on a mass basis at end-of...
The isotopic composition of mixed-oxide fuel (fabricated with both uranium and plutonium isotope) di...