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Geometry Optimization of Dispersed U Mo Fuel for Light Water Reactors

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초록

The Uranium/Molybdenum metallic fuel has been proposed as promising advanced fuel concept especially in the dispersed fuel geometry. The fuel is manufactured in the form of small fuel droplets (particles) placed in a fuel pin covered by a matrix. In addition to fuel particles, the pin contains voids necessary to compensate material swelling and release of fission gases from the fuel particles. When investigating this advanced fuel design, two important questions were raised. Can the dispersed fuel performance be analyzed using homogenization without significant inaccuracy and what size of fuel drops should be used for the fuel design to achieve optimal utilization? To answer, 2D burnup calculations of fuel assemblies with different fuel particle sizes were performed. The analysis was supported by an additional 3D fuel pin calculation with the dispersed fuel particle size variations. The results show a significant difference in the multiplication factor between the homogenized calculation and the detailed calculation with precise fuel particle geometry. The recommended fuel particle size depends on the final burnup to be achieved. As shown in the results, for lower burnup levels, larger fuel drops offer better multiplication factor. However, when higher burnup levels are required, then smaller fuel drops perform better.

Abstract

The Uranium/Molybdenum metallic fuel has been proposed as promising advanced fuel concept especially in the dispersed fuel geometry. The fuel is manufactured in the form of small fuel droplets (particles) placed in a fuel pin covered by a matrix. In addition to fuel particles, the pin contains voids necessary to compensate material swelling and release of fission gases from the fuel particles. When investigating this advanced fuel design, two important questions were raised. Can the dispersed fuel performance be analyzed using homogenization without significant inaccuracy and what size of fuel drops should be used for the fuel design to achieve optimal utilization? To answer, 2D burnup calculations of fuel assemblies with different fuel particle sizes were performed. The analysis was supported by an additional 3D fuel pin calculation with the dispersed fuel particle size variations. The results show a significant difference in the multiplication factor between the homogenized calculation and the detailed calculation with precise fuel particle geometry. The recommended fuel particle size depends on the final burnup to be achieved. As shown in the results, for lower burnup levels, larger fuel drops offer better multiplication factor. However, when higher burnup levels are required, then smaller fuel drops perform better.

참고문헌 (11)

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  5. Suwardi, "Thermal performance prediction of fuel pin containing u-9mo", zralloy produced by capillary impregnation technique for high burnup pwr, 2011, pp.7, ~
  6. Gamma Phase Uranium-Molybdenum Fuel Alloys, European Atomic Energy Community -EURATOM, "G. Beghi", Joint Nuclear Research Center, ~ (1968)
  7. P. Suk, "Performance of Vver-1200Reactor with Advanced Fuel and Cladding Materials", Nuclear Engineering and Design
  8. O. Safarzadeh, "Full-core reactor physics analysis for accident tolerant cladding in a vver-1000 reactor", Annals of Nuclear Energy, 155, pp.108163~ (2021)
  9. F. Fejt, "Study on neutronics of vver-1200 with accident tolerant fuel cladding", Annals of Nuclear Energy, 124, pp.579~591 (2019)
  10. Serpentea Continuous-Energy Monte Carlo Reactor Physics Burnup Calculation Code, vol. 4, "J. Leppanen", VTT Technical Research Centre of Finland, ~ (2013)
  11. Serpent e a Continuous-Energy Monte Carlo Reactor Physics Burnup Calculation Code, "J. Leppanen", ~ (2015)

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