Abstract
Accident-tolerant fuels and their licensing are one of the top priority strategic areas under “US Nuclear Regulation Committee (NRC) Systems Analysis Research Activities.” In addition, United States Department of Energy (DOE) has given significant attention for the advanced novel fuel, which can increase the burnup while exhibiting superior accident tolerance under “DOE Accident Tolerant Fuel Program” (under Fuel Cycle Research R&D). Therefore, this chapter focuses on the advanced composite accident-tolerant fuel systems. This chapter explains the integration of experiments with computational research efforts and data availability for the challenging qualification effort for accident-tolerant fuel concepts leveraging existing US DOE Accident-Tolerant Fuel Program’s industrial information. An overview of conventional empirical modeling reliance and its limitations in nuclear fuel development is also explained. The explanation of composite accident-tolerant fuel concepts leads to the concept development of digital twin and material twin technologies as a means to accelerate fuel qualification method, which can be leveraged in develo** and evaluating accident-tolerant fuel system. Most importantly, digital twin will pave the way for multi-criteria decision-making and risk-informed framework for both US DOE and US NRC for the new generation of accident-tolerant fuel concepts.
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References
S.B. Alam, C.S. Goodwin, G.T. Parks, Assembly-level analyses of accident-tolerant cladding concepts for a long-life civil marine SMR core using microheterogeneous duplex fuel. Prog. Nucl. Energy 111(September 2018), 24–41 (2019a)
S.B. Alam, R.G.G. de Oliveira, C.S. Goodwin, G.T. Parks, Coupled neutronic/thermal-hydraulic hot channel analysis of high power density civil marine SMR cores. Ann. Nucl. Energy 127, 400–411 (2019b)
B. Almutairi, S. Jaradat, D. Kumar, C.S. Goodwin, S. Usman, A. Alajo, S.B. Alam, Weight loss and burst testing investigations of sintered silicon carbide under oxidizing environments for next generation accident tolerant fuels for SMR applications. Mater. Today Commun. 30, 102958 (2022)
Ansys Software company. Ansys twin builder: Simulation-based hybrid analytic (datasheet), url: https://www.ansys.com/content/dam/product/digital-twin/twin-builder/ansys-twin-builder-technical-datasheet.pdf, (2022a)
Ansys Software company. Ansys twin builder (webpage), url: https://www.ansys.com/products/digital-twin/ansys-twin-builder, (2022b)
Ansys Software company. Build, validate and deploy simulation-based digital twins (video in the webpage), video url: https://share.vidyard.com/watch/myee78pdtm2c9xzybftsqv, page url: https://www.ansys.com/products/digital-twin/ansys-twin-builder, (2022c)
J. Bischoff, C. Delafoy, C. Vauglin, P. Barberis, C. Roubeyrie, D. Perche, D. Duthoo, F. Schuster, J.C. Brachet, E.W. Schweitzer, K. Nimishakavi, AREVA NP’s enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nucl. Eng. Technol. 50(2), 223–228 (2018)
S. Chakraborty, S. Adhikari, R. Ganguli, The role of surrogate models in the development of digital twins of dynamic systems. ar**v:2001.09292 [cs, stat], Jun 2020. ar**v: 2001.09292
Framatome. PROtect: The leading Enhanced Accident Tolerant Fuel Program, (n.d.)
George Jacobsen and General Atomics Electromagnetic. On the Path to a Nuclear Fuel Digital Twin : Modeling and Simulation of Silicon Carbide Cladding for Accelerated Fuel Qualification, (n.d.)
R. Ghanem, C. Soize, L. Mehrez, V. Aitharaju, Probabilistic learning and updating of a digital twin for composite material systems. Int. J. Num. Methods Eng., On line:1, (2020)
B. Gong, T. Yao, P. Lei, C. Lu, K.E. Metzger, E.J. Lahoda, F.A. Boylan, A. Mohamad, J. Harp, A.T. Nelson, J. Lian, U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels. J. Nucl. Mater. 534, 152147 (2020a)
B. Gong, T. Yao, P. Lei, J. Harp, A.T. Nelson, J. Lian, Spark plasma sintering (SPS) densified U3Si2 pellets: Microstructure control and enhanced mechanical and oxidation properties. J. Alloys Compd. 825, 154022 (2020b)
M. Große, M. Steinbrück, J. Stuckert, Steam and air oxidation behavior of nuclear fuel claddings at severe accident conditions. Mater. Res. Soc. Sympos. Proc. 1264, 215–220 (2010)
S.L. Hayes, J.K. Thomas, K.L. Peddicord, Material property correlations for uranium mononitride. IV. Thermodynamic properties. J. Nucl. Mater. 171(2–3), 300–318 (1990)
S. He, J. Cai, Thermal hydraulic analysis of the PWR with high uranium density accident tolerant fuels under accident transients with and without reactivity. Nucl. Eng. Des. 355(July), 110358 (2019)
S.M. Homam, S.A. Sheikh, Fiber-reinforced polymers exposed to nuclear power plant environment. J. Comp. Construct. 17(6), 04013007 (2013)
W. Huang, X. Rui, J. Yang, Q. Huang, H. Heng, Data-driven multiscale simulation of frp based on material twins. Compos. Struct. 256, 113013 (2021)
M. Jolkkonen, P. Malkki, K. Johnson, J. Wallenius, Uranium nitride fuels in superheated steam. J. Nucl. Sci. Technol. 54(5), 513–519 (2017)
C.A. Junior, J. Villanueva, I. Medeiros, R. Almeida, Digital twin design for thermal power plant cooling system using fuzzy system, in 2021 14th IEEE International Conference on Industry Applications (INDUSCON), (INDUSCON, 2021), pp. 661–666
B. Kochunas, X. Huan, Digital twin concepts with uncertainty for nuclear power applications. Energies 14(1414), 4235 (2021)
T. Koyanagi, Y. Katoh, G. Singh, M. Snead, SiC/SiC Cladding Materials Properties Handbook (Number August in M3-FT17OR020202104. U.S. Department of Energy, 2017)
D. Kumar, S.B. Alam, D. Vučinić, C. Lacor, Uncertainty quantification and robust optimization in engineering. Lect. Notes Mech. Eng., 63–93 (2020)
D. Kumar, S. Alam, T. Ridwan, C.S. Goodwin, Quantitative risk assessment of a high power density small modular reactor (SMR) core using uncertainty and sensitivity analyses. Energy 227, 120400 (2021)
D. Kumar, M. Marchi, S.B. Alam, C. Kavka, Y. Koutsawa, G. Rauchs, S. Belouettar, Multi-criteria decision making under uncertainties in composite materials selection and design. Compos. Struct. 279(February 2021), 114680 (2022)
L. Lin, H. Bao, N. Dinh, Uncertainty quantification and software risk analysis for digital twins in the nearly autonomous management and control systems: A review. Ann. Nucl. Energy 160, 108362 (2021)
J.P. Moore, D.L. Mcelroy, Thermal conductivity o f nearly stoic h iomet ric single-C rystal and polycrystalline UO. J. Am. Ceram. Soc. 54(1), 40–46 (1970)
A.T. Nelson, Stability of U3Si2 under H2O/PWR Coolant Conditions, LA-UR-17-30041 (Technical report, Los Alamos Natinal Laboratory (INL), 2017)
S. Nichenko, D. Staicu, Thermal conductivity of porous uo2: Molecular dynamics study. J. Nucl. Mater. 454(1), 315–322 (2014)
L.H. Ortega, B.J. Blamer, J.A. Evans, S.M. McDeavitt, Development of an accident-tolerant fuel composite from uranium mononitride (UN) and uranium sesquisilicide (U3 Si2) with increased uranium loading. J. Nucl. Mater. 471, 116–121 (2016)
L.J. Ott, K.R. Robb, D. Wang, Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. J. Nucl. Mater. 448(1–3), 520–533 (2014)
D. Ribeiro, M. Hedberg, S.C. Middleburgh, J. Wallenius, P. Olsson, D. Adorno, Oxidation of UN / U 2 N 3 -UO 2 composites : An evaluation of UO 2 as an oxidation barrier for the nitride phases. J. Nucl. Mater. 544, 152700 (2021)
Q. Shao, A. Makradi, D. Fiorelli, A. Mikdam, W. Huang, H. Hu, S. Belouettar, Material twin for composite material microstructure generation and reconstruction. Comp. Part C: Open Access 7, 100216 (2022)
B. Szpunar, J.A. Szpunar, Thermal conductivity of uranium nitride and carbide. Int. J. Nucl. Energy 2014, 1–7 (2014)
F. Tao, Q. Qi, L. Wang, A.Y.C. Nee, Digital twins and cyber–physical systems toward smart manufacturing and Industry 4.0: Correlation and comparison. Engineering 5(4), 653–661 (2019)
M.R. Tonks, D. Andersson, S.R. Phillpot, Y. Zhang, R. Williamson, C.R. Stanek, B.P. Uberuaga, S.L. Hayes, Mechanistic materials modeling for nuclear fuel performance. Ann. Nucl. Energy 105, 11–24 (2017)
M. Uno, T. Nishi, M. Takano, Thermodynamic and Thermophysical Properties of the Actinide Nitrides, Volume 2 (Elsevier Inc, 2012)
Westinghouse, EnCore Fuel (Westinghouse Electric Company, Pennsylvania, 2019), p. 16066
J.T. White, A.T. Nelson, Thermal conductivity of UO2+x and U4O9-y. J. Nucl. Mater. 443(1–3), 342–350 (2013)
J.T. White, A.T. Nelson, J.T. Dunwoody, D.D. Byler, D.J. Safarik, K.J. Mcclellan, Thermophysical properties of U3Si2 to 1773 K. J. Nucl. Mater. 464, 275–280 (2015)
J.H. Yang, D.J. Kim, K.S. Kim, Y.H. Koo, UO2-UN composites with enhanced uranium density and thermal conductivity. J. Nucl. Mater. 465, 509–515 (2015)
K. Yang, E. Kardoulaki, D. Zhao, A. Broussard, K. Metzger, J.T. White, M.R. Sivack, K.J. Mcclellan, E.J. Lahoda, J. Lian, Uranium nitride (UN) pellets with controllable microstructure and phase – Fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties. J. Nucl. Mater. 557, 153272 (2021)
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Kobayashi, K. et al. (2022). Digital Twin for Multi-criteria Decision-Making Framework to Accelerate Fuel Qualification for Accident-Tolerant Fuel Concepts. In: Fathi, M., Zio, E., Pardalos, P.M. (eds) Handbook of Smart Energy Systems. Springer, Cham. https://doi.org/10.1007/978-3-030-72322-4_160-1
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DOI: https://doi.org/10.1007/978-3-030-72322-4_160-1
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