Neutronic Performance Analysis of Inner-Side Chromium Coatings for Accident Tolerant Fuel

References

• S. BRAGG-SITTON, “Development of Advanced Accident-Tolerant Fuels for Commercial LWRs,” Nucl. News, 57, 3, 83 (2014).
   Google Scholar
• “Accident Tolerant Fuel Concepts for Light Water Reactors,” IAEA Tecdoc Series: Proceeding of a Technical Meeting Held at Oak Ridge National Laboratories, International Atomic Energy Agency (2014).
   Google Scholar
• J. BISCHOFF et al., “AREVA NP’s Enhanced Accident-Tolerant Fuel Developments: Focus on Cr-Coated M5 Cladding,” Nucl. Eng. Technol., 50, 2, 223 (Mar. 2018); https://doi.org/10.1016/j.net.2017.12.004.
   Web of Science ®Google Scholar
• M. SEVECEK and M. VALACH, “Evaluation Metrics Applied to Accident Tolerant Fuel Cladding Concepts for VVER Reactors,” Acta Polytech. CTU Proc., 4, 89 (2016); https://doi.org/10.14311/AP.2016.4.0089.
   Google Scholar
• B. CHENG, P. CHOU, and Y.-J. KIM, “Development of Mo-Based Accident Tolerant LWR Fuel Cladding,” IAEA-TECDOC–1797, International Atomic Energy Agency (2016).
   Google Scholar
• C. TANG et al., “Protective Coatings on Zirconium-Based Alloys as Accident-Tolerant Fuel (ATF) Claddings,” Corros. Rev., 35, 3, 141 (2017); https://doi.org/10.1515/corrrev-2017-0010.
   Web of Science ®Google Scholar
• H. CHEN, X. WANG, and R. ZHANG, “Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials,” Coatings, 10, 9, 808 (2020); https://doi.org/10.3390/coatings10090808.
   Web of Science ®Google Scholar
• J. YANG et al., “Review on Chromium Coated Zirconium Alloy Accident Tolerant Fuel Cladding,” J. Alloys Compd., 895, 1, 162450 (2022); https://doi.org/10.1016/j.jallcom.2021.162450.
   Web of Science ®Google Scholar
• Q. CHEN et al., “Microstructure and High-Temperature Steam Oxidation Properties of Thick Cr Coatings Prepared by Magnetron Sputtering for Accident Tolerant Fuel Claddings: The Role of Bias in the Deposition Process,” Corros. Sci., 165, 108378 (2020); https://doi.org/10.1016/j.corsci.2019.108378.
   Web of Science ®Google Scholar
• E. KASHKAROV et al., “Recent Advances in Protective Coatings for Accident Tolerant Zr-Based Fuel Claddings,” Coatings, 11, 5, 557 (2021); https://doi.org/10.3390/coatings11050557.
   Web of Science ®Google Scholar
• K. A. TERRANI, “Accident Tolerant Fuel Cladding Development: Promise, Status, and Challenges,” J. Nucl. Mater., 501, 13 (2018); https://doi.org/10.1016/j.jnucmat.2017.12.043.
   Web of Science ®Google Scholar
• J. C. BRACHET et al., “DLI-MOCVD CrxCy Coating to Prevent Zr-Based Cladding from Inner Oxidation and Secondary Hydriding upon LOCA Conditions,” J. Nucl. Mater., 550, 152953 (2021); https://doi.org/10.1016/j.jnucmat.2021.152953.
   Web of Science ®Google Scholar
• D. A. POWERS and R. O. MEYER, “Cladding Swelling and Rupture Models for LOCA Analysis,” Technical Report NUREG-0630, U.S. Nuclear Regulatory Commission (Apr. 1980).
   Google Scholar
• “State-of-the-Art Report on Light Water Reactor Accident-Tolerant Fuels,” NEA No. 7317, Organisation for Economic Co-Operation and Development, Nuclear Energy Agency (2018).
   Google Scholar
• A. MICHAU et al., “Inner-Side Coatings for Advanced Fuel Claddings Processed by DLI-MOCVD,” Proc. 2017 Water Reactors Fuel Performance Mtg., Jeju Island, South Korea, September 10–14, 2017.
   Google Scholar
• F. ADDOU et al., “Two-Sided Protection for Zirconium-Based Nuclear Fuel Cladding,” Proc. Int. Nuclear Fuel Cycle Conf. TOP FUEL 2019, Seattle, Washington, September 22–27, 2019.
   Google Scholar
• A. MICHAU et al., “Evidence for a Cr Metastable Phase as a Tracer in DLI-MOCVD Chromium Hard Coatings Usable in High Temperature Environment,” Appl. Surf. Sci., 422, 198 (2017); https://doi.org/10.1016/j.apsusc.2017.05.253.
   Web of Science ®Google Scholar
• A. MICHAU et al., “Chromium Carbide Growth at Low Temperature by a Highly Efficient DLI-MOCVD Process in Effluent Recycling Mode,” Surf. Coat. Technol., 332, 96 (2017); https://doi.org/10.1016/j.surfcoat.2017.06.077.
   Web of Science ®Google Scholar
• A. MICHAU et al., “High-Temperature Oxidation Resistance of Chromium-Based Coatings Deposited by DLI-MOCVD for Enhanced Protection of the Inner Surface of Long Tubes,” Surf. Coat. Technol., 349, 1048 (2018); https://doi.org/10.1016/j.surfcoat.2018.05.088.
   Web of Science ®Google Scholar
• A. MICHAU et al., “Chromium Carbide Growth by Direct Liquid Injection Chemical Vapor Deposition in Long and Narrow Tubes, Experiments, Modelling and Simulation,” Coatings, 8, 6, 220 (2018); https://doi.org/10.3390/coatings8060220.
   Web of Science ®Google Scholar
• F. FEJT et al., “Study on Neutronics of VVER-1200 with Accident Tolerant Fuel Cladding,” Ann. Nucl. Energy, 124, 579 (2019); https://doi.org/10.1016/j.anucene.2018.10.040.
   Web of Science ®Google Scholar
• I. YOUNKER and M. FRATONI, “Neutronic Evaluation of Coating and Cladding Materials for Accident Tolerant Fuels,” Prog. Nucl. Energy, 88, 10 (2016); https://doi.org/10.1016/j.pnucene.2015.11.006.
   Web of Science ®Google Scholar
• O. NOVÁK and M. SEVECEK, “Neutronic Analysis of the Candidate Multi-Layer Cladding Materials with Enhanced Accident Tolerance for WWER Reactors,” Acta Polytech. CTU Proc., 14, 27 (2018); https://doi.org/10.14311/APP.2018.14.0027.
   Google Scholar
• R. H. KHLIFA, N. N. NIKITENKOV, and V. N. KUDIIAROV, “On the Use of Chromium Coating for Inner-Side Fuel Cladding Protection: Thickness Identification Based on Fission Fragments Implantation and Damage Profile,” Coatings, 11, 6, 710 (2021); https://doi.org/10.3390/coatings11060710.
   Web of Science ®Google Scholar
• R. H. KHLIFA and N. N. NIKITENKOV, “Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating,” J. Nucl. Eng. Radiat. Sci., 9, 1 (2023); https://doi.org/10.1115/1.4055012.
   Web of Science ®Google Scholar
• D. B. PELOWITZ, “MCNPX User’ S Manual Version 2.7.0,” LA-CP-11-00438, Los Alamos National Laboratory (2011).
   Google Scholar
• M. CHADWICK et al., “ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology,” Nucl. Data Sheets, 107, 12, 2931 (2006); https://doi.org/10.1016/j.nds.2006.11.001.
   Google Scholar
• S. J. GARDINER et al., “Comparison of ENDF71x and ENDF70 Using ICSBEP Criticality Benchmarks in MCNP6,” Trans. Am. Nucl. Soc., 109, 1, 874 (2013).
   Google Scholar
• “Thermal Performance of High Burn-Up LWR Fuel,” Proc. Seminar on Thermal Performance of High Burn-Up LWR Fuel, Cadarache, France, March 3–6, 1998, Organisation for Economic Co-Operation and Development, Nuclear Energy Agency ( 1998).
   Google Scholar