Fuel Melting Simulation with FRAPCON/FRAPTRAN Codes for the Power-to-Melt-and-Maneuverability Simulation Exercise and Consideration of Model Modifications

References

• OECD/NEA, “Second Framework for Irradiation Experiments (FIDES-II),” (2022); https://www.oecd-nea.org/jcms/pl_70867/second-framework-for-irradiation-experiments-fides-ii.
   Google Scholar
• 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.
   Google Scholar
• K. J. 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,” Technical Report PNNL-19418, Vol. 1 Rev. 2, Pacific Northwest National Laboratory (2015).
   Google Scholar
• K. J. GEELHOOD et al., “FRAPTRAN 2.0: A Computer Code for the Transient Analysis of Oxide Fuel Rods,” Technical Report PNNL-19400, Vol. 1 Rev. 2, Pacific Northwest National Laboratory (2016).
   Google Scholar
• D. D. LANNING, C. E. BEYER, and K. J. GEELHOOD, “FRAPCON-3 Updates, Including Mixed-Oxide Fuel Properties,” Technical Report PNNL11513, Pacific Northwest National Laboratory (2005).
   Google Scholar
• D. MANARA et al., “Melting of Stoichiometric and Hyperstoichiometric Uranium Dioxide,” J. Nucl. Mat., 342, 148 (2005); http://dx.doi.org/10.1016/j.jnucmat.2005.04.002.
   Web of Science ®Google Scholar
• W. G. LUSCHER and K. J. GEELHOOD, “Material Property Correlations: Comparisons Between FRAPCON-3.4, FRAPTRAN 1.4, and MATPRO,” PNNL-19417 NUREG/CR-7024 Pacific Northwest National Laboratory (2011).
   Google Scholar
• B. MIHAILA, M. STAN, and J. CRAPPS, “Impact of Thermal Conductivity Models on the Coupling of Heat Transport and Oxygen Diffusion in UO2 Nuclear Fuel Elements,” J. Nucl. Mater., 430, 221 (2012); http://dx.doi.org/10.1016/j.jnucmat.2012.07.007.
   Web of Science ®Google Scholar
• L. LEIBOWITZ et al., “Enthalpy of Liquid Uranium Dioxide to 3500 K,” J. Nucl. Mat., 39, 115 (1971); http://dx.doi.org/10.1016/0022-3115(71)90190-5.
   Web of Science ®Google Scholar
• K. J. GEELHOOD and W. G. LUSCHER, “FRAPTRAN-2.0: Integral Assessment,” PNNL-19400 Vol. 2, Rev. 2, Pacific Northwest National Laboratory (2016).
   Google Scholar
• L. ANDREW, “Thermomechanical Analysis of Innovative Nuclear Fuel Pin Designs,” MS Thesis, Department of Nuclear Science and Engineering, Massachusetts Institute of Technology (2010).
   Google Scholar
• 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 (2013); https://doi.org/10.1080/00295450.2023.2253660.
   Google Scholar
• G. BONNY, “Presentation of the HBC4 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code TRANSURANUS,” submitted to ANS Nuclear Technology.
   Google Scholar
• A. TOPTAN, D. J. KROPACZEK, and M. N. AVRAMOVA, “Gap Conductance Modeling II: Optimized Model for UO2-Zircaloy Interfaces,” Nucl. Eng. Des., 355, 110289 (2019); http://dx.doi.org/10.1016/j.nucengdes.2019.110289.
   Web of Science ®Google Scholar
• I. CLIFFORD, C. COZZO, and H. FERROUKHI, “First Assessments of the Dynamic Gap Conductance Model in TRACE,” Proc. 18th Int. Topl. Mtg. on Nuclear Reactor Thermal Hydraulics (NURETH-18), p. 4624, American Nuclear Society (2019).
   Google Scholar
• K. J. GEELHOOD, W. G. LUSCHER, and C. E. BEYER, “FRAPCON-4.0: Integral Assessment,” Vol. 2. Pacific Northwest National Laboratory (2015).
   Google Scholar
• G. KHVOSTOV, “Modeling of Central Void Formation in LWR Fuel Pellets due to High-Temperature Restructuring,” Nucl. Eng. Technol., 50, 1190 (2018); http://dx.doi.org/10.1016/j.net.2018.07.003.
   Web of Science ®Google Scholar
• T. ARIMA, “Melting Point of Thermal Conductivity of UO2- ZrO2 Solid Solution: Molecular Dynamics Simulation,” J. COmput. Chem. Jpn., 14–4, 97 (2015); http://dx.doi.org/10.2477/jccj.2015-0007.
   Google Scholar
• W. K. KIM, J. H. SHIM, and M. KAVIANY, “Thermophysical Properties of Liquid UO2, ZrO2 and Corium by Molecular Dynamics and Predictive Models,” Trans. Korean Nuclear Society Autumn Mtg., Gyeongju, Korea, October 26–28, 2016 (2016).
   Google Scholar
• G. PASTORE et al., “Modeling Fission Gas Behavior with the BISON Fuel Performance Code,” presented at the EHPG Mtg., Lillehammer, Norway, September 24–29, 2017 ( 2017).
   Google Scholar
• L. C. BERNARD, J. L. JACOUD, and P. VESCO, “An Efficient Model for the Analysis of Fission Gas Release,” J. Nucl. Mat., 302, 125 (2002); http://dx.doi.org/10.1016/S0022-3115(02)00793-6.
   Web of Science ®Google Scholar
• A. GERMAIN et al., “Modeling High Burnup Fuel Thermochemistry, Fission Product Release and Fuel Melting During the VERDON 1 and RT6 Tests,” J. Nucl. Mat., 561, 153527 (2022); http://dx.doi.org/10.1016/j.jnucmat.2022.153527.
   Web of Science ®Google Scholar