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- W181796553 abstract "Changes in the power output of nuclear fuel result in transient mechanical interactions between the Zircaloy fuel shealth, coolant, fission gas, and fuel which lead to plastic deformation of the fuel sheath. In order to predict the performance of nuclear fuels computer simulations are required describing the mechanical behavior of fuel sheathing over wide ranges of strain rates. A computer simulation is described incorporating three plastic deformation modes. At high stresses hardening due to irradiation damage and softening due to the removal of irradiation damage during straining (tensile mode) are incorporated. At intermediate stresses neutron flux enhances deformation but strain hardening occurs (primary creep mode). At low stresses the strain rate depends only on neutron flux and stress (steady state creep mode). The instantaneous strain rate at any time is the sum of the strain rates calculated for each mode but over much of the strain rate range one mode predominates. At any stress the contribution of primary creep can disappear with strain and steady state creep occurs. The use of this simulation in a computer program describing nuclear fuel behavior is summarized and the type of stress-strain-strain rate history experienced by fuel sheathing during reactor operation is demonstrated." @default.
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- W181796553 date "1976-01-01" @default.
- W181796553 modified "2023-09-23" @default.
- W181796553 title "Simulation of nuclear fuel sheath deformation following fuel power transients" @default.
- W181796553 hasPublicationYear "1976" @default.
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