Phase-field simulations of fission gas bubble growth and interconnection in U-(Pu)-Zr nuclear fuel

Journal Article · 27 January 2022 · Materials Theory

DOI: https://doi.org/10.1186/s41313-021-00041-5 · OSTI ID:1842529

Aagesen, Larry K. ; Casagranda, Albert; Matthews, Christopher; Beeler, Benjamin W.; Novascone, Stephen

Abstract The growth and interconnection of fission gas bubbles in the hotter central regions of U-(Pu)-Zr nuclear fuel has been simulated with a phase-field model. The Cahn-Hilliard equation was used to represent the two-phase microstructure, with a single defect species. The volume fraction of the bubble phase and surface area of the bubble-matrix interface were determined during growth and interconnection. Surface area increased rapidly during the initial stages of growth, then slowed and finally decreased as bubble interconnection began and coarsening acted to reduce surface area. The fraction of the bubbles vented to a simulation domain boundary, f _V , was quantified as a measure of the microstructure’s interconnectivity and plotted as a function of porosity p . The defect species diffusivity was varied; although changes in diffusivity significantly affected the microstructure, the plots of f _V vs. p did not change significantly. The percolation threshold p _c was calculated to be approximately 0.26, depending on the assumed diffusivity and using an initial bubble number density based on experimental observations. This is slightly smaller than the percolation threshold for continuum percolation of overlapping 3D spheres. The simulation results were used to parameterize two different engineering-scale swelling models for U-(Pu)-Zr in the nuclear fuel performance code BISON.

• Sponsoring Organization: USDOE
• OSTI ID: 1842529
• Journal Information: Materials Theory, Journal Name: Materials Theory Journal Issue: 1 Vol. 6; ISSN 2509-8012
• Publisher: Springer Science + Business MediaCopyright Statement
• Country of Publication: Switzerland
• Language: English