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- W1968635612 abstract "Abstract The reliability of nuclear fuel for LWR reactors is generally good, but there are still some failures caused by pellet-cladding interactions (stress corrosion). Only a very small fraction of the fuel pins in operation fail, and the nature of the failures indicates a statistical problem; therefore a statistical fuel model was developed. The statistical methods are either Monte Carlo simulation or a Taylor approximation. The statistical program utilizes a deterministic fuel performance code with a stress corrosion failure criterion, verified against experimental data. The failure probability for a power ramp was evaluated for different fuel designs and ramp conditions. It is shown that the failure probability can be quite large, even when a deterministic simulation (based on the average values for design and material data) is far from the failure criterion." @default.
- W1968635612 created "2016-06-24" @default.
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- W1968635612 date "1980-02-01" @default.
- W1968635612 modified "2023-09-24" @default.
- W1968635612 title "The statistical fuel model, FRP" @default.
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- W1968635612 doi "https://doi.org/10.1016/0029-5493(80)90164-8" @default.
- W1968635612 hasPublicationYear "1980" @default.
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