Phase-field simulations of fission gas bubble growth and interconnection in U-(Pu)-Zr nuclear fuel
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...
| Main Authors: | , , , , |
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| Format: | Article |
| Language: | English |
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SpringerOpen
2022-01-01
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| Series: | Materials Theory |
| Subjects: | |
| Online Access: | https://doi.org/10.1186/s41313-021-00041-5 |
| _version_ | 1819231367656898560 |
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| author | Larry K. Aagesen Albert Casagranda Christopher Matthews Benjamin W. Beeler Stephen Novascone |
| author_facet | Larry K. Aagesen Albert Casagranda Christopher Matthews Benjamin W. Beeler Stephen Novascone |
| author_sort | Larry K. Aagesen |
| collection | DOAJ |
| description | 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. |
| first_indexed | 2024-12-23T11:43:50Z |
| format | Article |
| id | doaj.art-327dda3bb1264f6cb1bc6147b50da309 |
| institution | Directory Open Access Journal |
| issn | 2509-8012 |
| language | English |
| last_indexed | 2024-12-23T11:43:50Z |
| publishDate | 2022-01-01 |
| publisher | SpringerOpen |
| record_format | Article |
| series | Materials Theory |
| spelling | doaj.art-327dda3bb1264f6cb1bc6147b50da3092022-12-21T17:48:23ZengSpringerOpenMaterials Theory2509-80122022-01-016112010.1186/s41313-021-00041-5Phase-field simulations of fission gas bubble growth and interconnection in U-(Pu)-Zr nuclear fuelLarry K. Aagesen0Albert Casagranda1Christopher Matthews2Benjamin W. Beeler3Stephen Novascone4Computational Mechanics and Materials Department, Idaho National LaboratoryTerraPower, LLCMaterials Science and Technology Division, Los Alamos National LaboratoryDepartment of Nuclear Engineering, North Carolina State UniversityComputational Mechanics and Materials Department, Idaho National LaboratoryAbstract 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.https://doi.org/10.1186/s41313-021-00041-5Phase-fieldFission gas bubbleUraniumZirconium |
| spellingShingle | Larry K. Aagesen Albert Casagranda Christopher Matthews Benjamin W. Beeler Stephen Novascone Phase-field simulations of fission gas bubble growth and interconnection in U-(Pu)-Zr nuclear fuel Materials Theory Phase-field Fission gas bubble Uranium Zirconium |
| title | Phase-field simulations of fission gas bubble growth and interconnection in U-(Pu)-Zr nuclear fuel |
| title_full | Phase-field simulations of fission gas bubble growth and interconnection in U-(Pu)-Zr nuclear fuel |
| title_fullStr | Phase-field simulations of fission gas bubble growth and interconnection in U-(Pu)-Zr nuclear fuel |
| title_full_unstemmed | Phase-field simulations of fission gas bubble growth and interconnection in U-(Pu)-Zr nuclear fuel |
| title_short | Phase-field simulations of fission gas bubble growth and interconnection in U-(Pu)-Zr nuclear fuel |
| title_sort | phase field simulations of fission gas bubble growth and interconnection in u pu zr nuclear fuel |
| topic | Phase-field Fission gas bubble Uranium Zirconium |
| url | https://doi.org/10.1186/s41313-021-00041-5 |
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