References
- M. BALES, “The NEA Framework for Irradiation Experiments (FIDES): A New Future for International Collaboration on Nuclear Fuel Research,” Proc. TopFuel 2022 Conf., Raleigh, North Carolina, October 9–13, 2022, American Nuclear Society (2022); https://doi.org/10.13182/TopFuel22-39084.
- “ Second Framework for Irradiation Experiments (FIDES‑II),” OECD Nuclear Energy Agency; https://www.oecd-nea.org/jcms/pl_70867/.
- V. ARIMESCU et al., “Third SCIP Modeling Workshop: Beneficial Impact of Slow Power Ramp on PCI Performance,” Proc. WRFPM 2014, Sendai, Japan, September 14–17, Paper No. 100045 (2014).
- V. D’AMBROSI et al., “P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments,” Nucl. Technol., 210, 2, 189 (2024); 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 (2024); https://doi.org/10.1080/00295450.2023.2253660.
- G. BONNY et al., “The UO2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program,” Nucl. Technol., 210, 2, 216 (2024); https://doi.org/10.1080/00295450.2023.2264505.
- J. SERCOMBE et al., “2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel Performance Code ALCYONE,” Nucl. Technol., 210, 2, 269 (2024); https://doi.org/10.1080/00295450.2023.2188138.
- A. MOHAMAD and Y. UDAGAWA, “Modeling of the P2M Past Fuel Melting Experiments with the FEMAXI-8 Code,” Nucl. Technol., 210, 2, 245 (2024); https://doi.org/10.1080/00295450.2023.2185061.
- J. CORSON, A. CHUNG, and S. MULLER, “Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1,” Nucl. Technol., 210, 2, 261 (2024); https://doi.org/10.1080/00295450.2023.2181042.
- A. CHAIEB et al., “Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code CYRANO3,” Nucl. Technol., 210, 2, 232 (2024); https://doi.org/10.1080/00295450.2023.2232664.
- D. ROZZIA et al., “Modeling of OECD/NEA P2M Benchmark Cases by Means of TRANSURANUS Code,” Nucl. Technol., 210, 2, 324 (2024); https://doi.org/10.1080/00295450.2023.2229186.
- K. INAGAKI, “Fuel Melting Simulation with FRAPCON/FRAPTRAN Codes for the Power-to-Melt-and-Maneuverability Simulation Exercise and Consideration of Model Modifications,” Nucl. Technol., 210, 2, 308 (2024); https://doi.org/10.1080/00295450.2023.2239041.
- A. FAYET et al., “Determination of the Gas Plenum Temperature of the P2M Instrumented Fuel Rodlets on the Basis of a Thermal-Hydraulic Study of the Belgian Reactor 2 Pressurized Water Capsule,” Nucl. Technol., 210, 2, 354 (2024); https://doi.org/10.1080/00295450.2023.2271222.