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Research Articles

Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1

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Pages 261-268 | Received 30 Sep 2022, Accepted 13 Feb 2023, Published online: 02 Mar 2023

References

  • K. GEELHOOD et al., “FRAPCON-4.0: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup,” PNNL-19418, Vol. 1, Rev. 2, Pacific Northwest National Laboratory (2015).
  • K. GEELHOOD and W. LUSCHER, “FRAPCON-4.0: Integral Assessment,” PNNL-19418, Vol. 2, Rev. 2, Pacific Northwest National Laboratory (2015).
  • K. GEELHOOD et al., “FRAPTRAN-2.0: A Computer Code for the Transient Analysis of Oxide Fuel Rods,” PNNL-19400, Vol. 1, Rev. 2, Pacific Northwest National Laboratory (2016).
  • K. GEELHOOD and W. LUSCHER, “FRAPTRAN-2.0: Integral Assessment,” PNNL-19418, Vol. 2, Rev. 2, Pacific Northwest National Laboratory (2015).
  • K. GEELHOOD et al., “FAST-1.0.1: A Computer Code for Thermal-Mechanical Nuclear Fuel Analysis Under Steady- State and Transients,” PNNL-31160, Pacific Northwest National Laboratory (2021).
  • K. GEELHOOD et al., “MatLib-1.0: Nuclear Material Properties Library,” PNNL-31158, Pacific Northwest National Laboratory (2021).
  • K. GEELHOOD et al., “FAST-1.0.1: Integral Assessment,” PNNL-31161, Pacific Northwest National Laboratory (2021).
  • “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,” NUREG-0800, U.S. Nuclear Regulatory Commission (2007).
  • V. D’AMBROSI et al., “P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments,” Nucl. Technol., 210, 2, 189 (2023); https://doi.org/10.1080/00295450.2023.2194270.
  • V. D’AMBROSI et al., “Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE,” Nucl. Technol., 210, 2, 285 (2023); https://doi.org/10.1080/00295450.2023.2253660.
  • D. ROZZIA et al., “Modeling of OECD/NEA P2M Benchmark Cases by Means of TRANSURANUS Code,” Nucl. Technol., 210, 2, 324 (2023); https://doi.org/10.1080/00295450.2023.2229186.
  • M. BOHN, “FRACAS: A Subcode for the Analysis of Fuel Pellet-Cladding Mechanical Interaction,” TREE-NUREG-1028, EG&E Idaho, Inc. (1977).
  • A. KNUUTILA, “Improvements on FRAPCON-3/FRAPTRAN Mechanical Modeling,” VTTR-11337-06, VTT Technical Research Centre of Finland (2006).
  • K. FORSBERG and A. MASSIH, “Diffusion Theory of Fission Gas Migration in Irradiated Nuclear Fuel UO2,” J. Nucl. Mater., 135, 2–3, 140 (1985); https://doi.org/10.1016/0022-3115(85)90071-6.
  • A. BOOTH, “A Method of Calculating Fission Gas Diffusion from UO2 Fuel and Its Application to the X-2 Loop Test,” AECL-496, Atomic Energy of Canada Limited (1957).

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