TY - JOUR
T1 - Grain boundary percolation modeling of fission gas release in oxide fuels
AU - Millett, Paul C.
AU - Tonks, Michael R.
AU - Biner, S. B.
N1 - Funding Information:
The authors gratefully acknowledge financial support from the Nuclear Energy Modeling and Simulation (NEAMS) program within the US Department of Energy. In addition, we thank Rich Williamson (INL) for insightful conversations.
PY - 2012/5
Y1 - 2012/5
N2 - We present a new approach to fission gas release modeling in oxide fuels based on grain boundary network percolation. The method accounts for variability in the bubble growth and coalescence rates on individual grain boundaries, and the resulting effect on macroscopic fission gas release. Two-dimensional representations of fuel pellet microstructures are considered, and the resulting gas release rates are compared with traditional 2-stage Booth models, which do not account for long-range percolation on grain boundary networks. The results show that accounting for the percolation of saturated grain boundaries can considerably reduce the predicted gas release rates, particularly when gas resolution is considered.
AB - We present a new approach to fission gas release modeling in oxide fuels based on grain boundary network percolation. The method accounts for variability in the bubble growth and coalescence rates on individual grain boundaries, and the resulting effect on macroscopic fission gas release. Two-dimensional representations of fuel pellet microstructures are considered, and the resulting gas release rates are compared with traditional 2-stage Booth models, which do not account for long-range percolation on grain boundary networks. The results show that accounting for the percolation of saturated grain boundaries can considerably reduce the predicted gas release rates, particularly when gas resolution is considered.
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U2 - 10.1016/j.jnucmat.2012.03.006
DO - 10.1016/j.jnucmat.2012.03.006
M3 - Article
AN - SCOPUS:84859062001
VL - 424
SP - 176
EP - 182
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
SN - 0022-3115
IS - 1-3
ER -