References
- K. A. TERRANI et al., “Accelerating Nuclear Fuel Development and Qualification: Engineering-Scale Modeling and Simulation Integrated with Separate Effects Testing,” J. Nucl. Mater., 539, 152267 (2020); https://doi.org/10.1016/j.jnucmat.2020.152267.
- P. J. PAPPANO et al., “A Novel Approach to Fabricating Fuel Compacts for the Next Generation Nuclear Plant (NGNP),” J. Nucl. Mater., 381, 25 (2008); https://doi.org/10.1016/j.jnucmat.2008.07.032.
- P. A. DEMKOWICZ, B. LIU, and J. D. HUNN, “Coated Particle Fuel: Historical Perspectives and Current Progress,” J. Nucl. Mater., 515, 434 (2019); https://doi.org/10.1016/j.jnucmat.2018.09.044.
- K. TERRANI, B. JOLLY, and M. TRAMMELL, “3D Printing of High-Purity Silicon Carbide,” J. American Ceramic Soc., 103, 1575 (2019).
- B. ADE et al., “Particle Packing Characteristics in Dense TRISO/SiC Fuel Elements and the Impact on Neutronics and Thermomechanics,” Trans. Am. Nucl. Soc., 123, 1422 (2020); https://doi.org/10.13182/T123-33390.
- K. A. TERRANI, L. L. SNEAD, and J. C. GEHIN, “Microencapsulated Fuel Technology for Commercial Light Water and Advanced Reactor Application,” J. Nucl. Mater., 427, 209 (2012); https://doi.org/10.1016/j.jnucmat.2012.05.021.
- J. D. HALES et al., “Multidimensional Multiphysics Simulation of TRISO Particle Fuel,” J. Nucl. Mater., 443, 531 (2013); https://doi.org/10.1016/j.jnucmat.2013.07.070.
- R. L. WILLIAMSON et al., “Multidimensional Multiphysics Simulation of Nuclear Fuel Behavior,” J. Nucl. Mater., 423, 149 (2012); https://doi.org/10.1016/j.jnucmat.2012.01.012.
- D. SCHAPPEL et al., “Modeling the Performance of TRISO-based Fully Ceramic Matrix (FCM) Fuel in an LWR Environment Using BISON,” Nucl. Eng. Des., 335, 116 (2018); https://doi.org/10.1016/j.nucengdes.2018.05.018.
- D. SCHAPPEL, G. PASTORE, and K. A. TERRANI, “Modeling Interface Debonding in Coated Fuel Particles with BISON,” Nucl. Sci. Eng., 196, 276 (2021); https://doi.org/10.1080/00295639.2021.1955590.
- J. D. HUNN et al., “PIE on Safety-Tested AGR-1 Compact 4-2-2,” Oak Ridge National Laboratory (2015).
- J. D. HUNN et al., “PIE on Safety-Tested AGR-1 Compact 5-1-1,” Oak Ridge National Laboratory (2015).
- K. A. TERRANI, B. C. JOLLY, and J. M. HARP, “Uranium Nitride Tristructural-Isotropic Fuel Particle,” J. Nucl. Mater., 531, 152034 (2020).
- R. L. SEIBERT et al., “Production and Characterization of TRISO Fuel Particles with Multilayered SiC,” J. Nucl. Mater., 515, 215 (2019); https://doi.org/10.1016/j.jnucmat.2018.12.024.
- D. PETTI et al., “Development of Improved Models and Designs for Coated-Particle Gas Reactor Fuels,” U.S. Department of Energy: Office of Scientific and Technical Information (2004).
- M. BEN-BELGACEM et al., “Thermo-mechanical Analysis of LWR SiC/SiC Composite Cladding,” J. Nucl. Mater., 447, 1–3, 125 (2014); https://doi.org/10.1016/j.jnucmat.2014.01.006.
- Y. KATOH et al., “Continuous SiC Fiber, CVI SiC Matrix Composites for Nuclear Applications: Properties and Irradiation Effects,” J. Nucl. Mater., 448, 1–3, 448 (2014); https://doi.org/10.1016/j.jnucmat.2013.06.040.
- R. J. PRICE, “Properties of Silicon Carbide for Nuclear Fuel Particle Coatings,” Nucl. Technol., 35, 2, 320 (1977); https://doi.org/10.13182/NT77-A31892.
- L. L. SNEAD et al., “Handbook of SiC Properties for Fuel Performance Modeling,” J. Nucl. Mater., 371, 1–3, 329 (2007); https://doi.org/10.1016/j.jnucmat.2007.05.016.
- T. S. BYUN et al., “Mechanical and Thermophysical Properties of 3D-Printed SiC-FY2,” ORNL/SPR-2020/1545, Oak Ridge National Laboratory (2020).
- S. L. HAYES, J. K. THOMAS, and K. L. PEDDICORD, “Material Property Correlations for Uranium Mononitride: I. Physical Properties,” J. Nucl. Mater., 171, 262 (1990); https://doi.org/10.1016/0022-3115(90)90374-V.
- Y. RASHID, R. DUNHAM, and R. MONTGOMERY, “Fuel Analysis and Licensing Code: FALCON MOD01,” EPRI Report 1011308, Electric Power Research Institute (2004).
- J. K. HOHORST, “SCDAP/RELAP5/MOD2 Code Manual, Volume 4: MATPRO—A Library of Materials Properties for Light-Water-Reactor Accident Analysis,” EG&G Idaho Report NUREG/CR 5273, U.S. Nuclear Regulatory Agency (1990).
- S. KONDO, Y. KATOH, and L. L. SNEAD, “Concentric Ring on Ring Test for Unirradiated and Irradiated Miniature SiC Specimens,” J. Nucl. Mater., 417, 406 (2011); https://doi.org/10.1016/j.jnucmat.2010.12.083.
- H. NABIELEK et al., “Fuel for Pebble-Bed HTRs,” Nucl. Eng. Des., 78, 155 (1984); https://doi.org/10.1016/0029-5493(84)90301-7.
- C. ANG, L. SNEAD, and Y. KATO, “A Logical Approach for Zero-Rupture Fully Ceramic Microencapsulated (FCM) Fuels via Pressure-Assisted Sintering Route,” J. Nucl. Mater., 531, 151987 (2020).
- K. MINATO and K. FUKUDA, “Chemical Vapor Deposition of Silicon Carbide for Coated Fuel Particles,” J. Nucl. Mater., 149, 233 (1987); https://doi.org/10.1016/0022-3115(87)90482-X.
- “TecDoc 1674 Advances in High Temperature Gas Cooled Reactor Fuel Technology,” International Atomic Energy Agency (2012).