This report presents studies to assess reactivity margins and loading curves for pressurized water reactor (PWR) burnup-credit criticality safety evaluations. The studies are based on a generic high-density 32-assembly cask and systematically vary individual calculational (depletion and criticality) assumptions to demonstrate the impact on the predicted effective neutron multiplication factor, k{sub eff}, and burnup-credit loading curves. The purpose of this report is to provide a greater understanding of the importance of input parameter variations and quantify the impact of calculational assumptions on the outcome of a burnup-credit evaluation. This study should provide guidance to regulators and industry on the technical areas where impr...
We present a summary of the actinide-plus-fission-product burnup credit criticality safety licensing...
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuc...
The purpose of this activity is to develop a representative ''limiting'' axial burnup profile for pr...
This report proposes and documents a computational benchmark problem for the estimation of the addit...
Spent fuel transportation and storage cask designs based on a burnup credit approach must consider i...
This paper summarizes efforts related to developing a technically justifiable approach for addressin...
This paper has presented the results of a computational benchmark and independent calculations to ve...
The Interim Staff Guidance on burnup credit (ISG-8) issued by the United States Nuclear Regulatory C...
In the past, criticality safety analyses for spent fuel storage and transport canisters assumed the ...
This study performed criticality analysis for the GBC-68 storage cask loaded with boiling water reac...
The concept of taking credit for the reduction in reactivity of burned or spent nuclear fuel (SNF) d...
In 1999 the U.S. Nuclear Regulatory Commission (U.S. NRC) initiated a research program to support th...
The Interim Staff Guidance on burnup credit (ISG-8) for pressurized water reactor (PWR) spent nuclea...
Current criticality safety calculations for the transportation of irradiated LWR fuel make the very ...
We present a summary of the actinide-plus-fission-product burnup credit criticality safety licensing...
We present a summary of the actinide-plus-fission-product burnup credit criticality safety licensing...
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuc...
The purpose of this activity is to develop a representative ''limiting'' axial burnup profile for pr...
This report proposes and documents a computational benchmark problem for the estimation of the addit...
Spent fuel transportation and storage cask designs based on a burnup credit approach must consider i...
This paper summarizes efforts related to developing a technically justifiable approach for addressin...
This paper has presented the results of a computational benchmark and independent calculations to ve...
The Interim Staff Guidance on burnup credit (ISG-8) issued by the United States Nuclear Regulatory C...
In the past, criticality safety analyses for spent fuel storage and transport canisters assumed the ...
This study performed criticality analysis for the GBC-68 storage cask loaded with boiling water reac...
The concept of taking credit for the reduction in reactivity of burned or spent nuclear fuel (SNF) d...
In 1999 the U.S. Nuclear Regulatory Commission (U.S. NRC) initiated a research program to support th...
The Interim Staff Guidance on burnup credit (ISG-8) for pressurized water reactor (PWR) spent nuclea...
Current criticality safety calculations for the transportation of irradiated LWR fuel make the very ...
We present a summary of the actinide-plus-fission-product burnup credit criticality safety licensing...
We present a summary of the actinide-plus-fission-product burnup credit criticality safety licensing...
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuc...
The purpose of this activity is to develop a representative ''limiting'' axial burnup profile for pr...