Thermochemically-informed mass transport model for interdiffusion of U and Zr in irradiated U-Pu-Zr fuel with fission products
| Autor: | Srdjan Simunovic, Max Poschmann, Theodore M. Besmann, Kevin T. Clarno, Markus H.A. Piro |
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| Rok vydání: | 2021 |
| Předmět: |
Nuclear and High Energy Physics
Nuclear fission product Work (thermodynamics) Fission products Nuclear fuel Thermodynamics Context (language use) 02 engineering and technology 021001 nanoscience & nanotechnology 7. Clean energy 01 natural sciences 010305 fluids & plasmas Nuclear Energy and Engineering 0103 physical sciences Thermochemistry General Materials Science Redistribution (chemistry) 0210 nano-technology Burnup |
| Zdroj: | Journal of Nuclear Materials. 554:153089 |
| ISSN: | 0022-3115 |
| Popis: | A new formulation for redistribution of constituents in metallic U-Pu-Zr nuclear fuel is presented that can incorporate the contributions from fission products. The formulation is based on the thermodynamic driving forces derived from the generalized chemical potential that includes effects of composition and temperature. As a result, the redistribution model can readily account for the composition changes due to the generation of fission products while using only a limited set of transport coefficients. The thermodynamic model for the metallic fuel and thermochemistry solver Thermochimica were coupled with the nuclear fuel performance code BISON to implement the redistribution model. The simulations reproduce an experimentally observed Zr-depletion zone in the mid-radius region of an irradiated fuel slug. The generation of fission products during burnup is shown to have a stabilizing effect on the fuel chemistry, slowing the rate of U-Zr interdiffusion and reducing the size of the Zr-depleted zone. The overall objective of the work is to advance predictive capabilities of fission product behaviour in U-Zr metallic fuel in the context of fuel performance and safety. |
| Databáze: | OpenAIRE |
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