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Radiation re-solution of fission gas in non-oxide nuclear fuel Public Deposited

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https://ir.library.oregonstate.edu/concern/articles/d791sh46n

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Abstract
  • Renewed interest in fast nuclear reactors is creating a need for better understanding of fission gas bubble behavior in non-oxide fuels. Collisions between fission fragments and their subsequent cascades can knock fission gas atoms out of bubbles and back into the fuel lattice, resulting in a loss term for the bubble. By assuming these collisions can be treated as binary collisions, we calculated a re-solution parameter as a function of bubble radius. The calculations showed that there is a sharp decrease as bubble size increases until about 100 nm when the re-solution parameter stays nearly constant. The bubble size dependence may explain the large bubble size distribution found in some uranium carbide and nitride fuels. Furthermore, our model shows ion cascades created in the fuel result in many more implanted fission gas atoms than collisions directly with fission fragments. Utilization of our calculated re-solution parameter can be used to find a re-solution rate for future bubble behavior simulations.
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  • Matthews, C., Schwen, D., & Klein, A. C. (2015). Radiation re-solution of fission gas in non-oxide nuclear fuel. Journal of Nuclear Materials, 457, 273-278. doi:10.1016/j.jnucmat.2014.11.108
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  • 457
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  • This research is being performed using funding received from the DOE Office of Nuclear Energy's Nuclear Energy University Programs.
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