Data processing: structural design – modeling – simulation – and em – Simulating nonelectrical device or system
Reexamination Certificate
2007-09-04
2007-09-04
Frejd, Russell (Department: 2128)
Data processing: structural design, modeling, simulation, and em
Simulating nonelectrical device or system
C703S002000
Reexamination Certificate
active
10879358
ABSTRACT:
A method, arrangement and computer program is described for determining a set of standardized rod types for use in a nuclear reactor core. The method may include defining a set of rod type-related limits, and determining, based on the limits, an initial population of rod types to be evaluated for use in cores of a selected number of nuclear reactor plants. Based on the initial population of rod types a database of selectable fresh fuel bundle designs applicable to the one or more cores may be generated. Bundle data related to at least a subset of the selectable fresh fuel bundle designs may be retrieved from the database, and a target number of rod types may be selected from the initial population based on the retrieved bundle data as the set of standardized rod types.
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Asgari Mehdi
Cline William Charles
Kropaczek David Joseph
Oyarzun Christian Carlos
Russell, II William Earl
Frejd Russell
Global Nuclear Fuel-Americas LLC
Harness & Dickey & Pierce P.L.C.
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