DOI QR코드

DOI QR Code

Development of Cr cold spray-coated fuel cladding with enhanced accident tolerance

  • Sevecek, Martin (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology) ;
  • Gurgen, Anil (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology) ;
  • Seshadri, Arunkumar (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology) ;
  • Che, Yifeng (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology) ;
  • Wagih, Malik (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology) ;
  • Phillips, Bren (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology) ;
  • Champagne, Victor (ARL Cold Spray Center, U.S. Army Research Laboratory) ;
  • Shirvan, Koroush (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology)
  • 투고 : 2017.11.18
  • 심사 : 2017.12.22
  • 발행 : 2018.03.25

초록

Accident-tolerant fuels (ATFs) are currently of high interest to researchers in the nuclear industry and in governmental and international organizations. One widely studied accident-tolerant fuel concept is multilayer cladding (also known as coated cladding). This concept is based on a traditional Zr-based alloy (Zircaloy-4, M5, E110, ZIRLO etc.) serving as a substrate. Different protective materials are applied to the substrate surface by various techniques, thus enhancing the accident tolerance of the fuel. This study focuses on the results of testing of Zircaloy-4 coated with pure chromium metal using the cold spray (CS) technique. In comparison with other deposition methods, e.g., Physical vapor deposition (PVD), laser coating, or Chemical vapor deposition techniques (CVD), the CS technique is more cost efficient due to lower energy consumption and high deposition rates, making it more suitable for industry-scale production. The Cr-coated samples were tested at different conditions ($500^{\circ}C$ steam, $1200^{\circ}C$ steam, and Pressurized water reactor (PWR) pressurization test) and were precharacterized and postcharacterized by various techniques, such as scanning electron microscopy, Energy-dispersive X-ray spectroscopy (EDX), or nanoindentation; results are discussed. Results of the steady-state fuel performance simulations using the Bison code predicted the concept's feasibility. It is concluded that CS Cr coating has high potential benefits but requires further optimization and out-of-pile and in-pile testing.

키워드

참고문헌

  1. J.C. Brachet, C. Lorrette, A. Michaux, C. Sauder, I. Idarraga-Trujillo, M. Le Saux, M. Le Flem, F. Schuster, A. Billard, E. Monsifrot, E. Torres, F. Rebillat, J. Bischoff, A. Ambard, CEA studies on advanced nuclear fuel claddings for enhanced accident tolerant LWRs fuel (LOCA and beyond LOCA conditions), in: Fontevraud 8: Conference on Contribution of Materials Investigations and Operating Experience to LWRs' Safety, Performance and Reliability; Avignon (France), 2015, 15-18 Sep 2014; 15 refs, 32 p.
  2. H.-G. Kim, J.-H. Yang, W.-J. Kim, Y.-H. Koo, Development status of accident-tolerant fuel for light water reactors in Korea, Nucl. Eng. Technol. 48 (1) (Feb. 2016) 1-15. https://doi.org/10.1016/j.net.2015.11.011
  3. B. Maier, et al., Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors, JOM 70 (2) (2018).
  4. J. Krejci, M. Sevecek, L. Cvrcek, Development of chromium and chromium nitride coated cladding for VVER reactors, in: Proceedings, WRFPM, 2017. A-131.
  5. А.S. Kuprin, et al., Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air, J. Nucl. Mater. 465 (Oct. 2015) 400-406. https://doi.org/10.1016/j.jnucmat.2015.06.016
  6. R. Van Nieuwenhove, V. Andersson, J. Balak, B. Oberlander, In-pile testing of CrN, TiAlN and AlCrN coatings on Zircaloy cladding in the halden reactor, in: 18th International Symposium on Zirconium in the Nuclear Industry, 2016.
  7. K. Daub, R. Van Nieuwenhove, H. Nordin, Investigation of the impact of coatings on corrosion and hydrogen uptake of Zircaloy-4, J. Nucl. Mater. 467 (Dec. 2015) 260-270. https://doi.org/10.1016/j.jnucmat.2015.09.041
  8. ASTM International, ASTM B614-b616 Standard Practice for Descaling and Cleaning Zirconium and Zirconium Alloy Surfaces, West Conshohocken, PA, 2016.
  9. C.W. Weaver, Irradiation and the ductility of chromium, Scr. Metall. 2 (8) (Aug. 1968) 463-466. https://doi.org/10.1016/0036-9748(68)90195-6
  10. U. Holzwarth, H. Stamm, Mechanical and thermomechanical properties of commercially pure chromium and chromium alloys, J. Nucl. Mater. 300 (2) (2002) 161-177. https://doi.org/10.1016/S0022-3115(01)00745-0
  11. J.R. Stephens, W.D. Klopp, High-temperature creep of polycrystalline chromium, J. Common Met. 27 (1) (1972) 87-94. https://doi.org/10.1016/0022-5088(72)90108-7
  12. I. Idarraga-Trujillo, et al., Assessment at CEA of coated nuclear fuel cladding for LWRS with increased margins in LOCA and beyond LOCA conditions, in: Conference Paper LWR Fuel Performance Meeting, Top Fuel 2013, vol. 2, 2013, pp. 860-867.
  13. H.-G. Kim, I.-H. Kim, Y.-I. Jung, D.-J. Park, J.-Y. Park, Y.-H. Koo, Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating, J. Nucl. Mater. 465 (Oct. 2015) 531-539. https://doi.org/10.1016/j.jnucmat.2015.06.030
  14. R. Tucker Jr., Thermal spray technology, ASM Handbook, Volume 5A, Plast. Ind. 335 (2013) 336.
  15. V.K. Champagne, D. Helfritch, P. Leyman, S. Grendahl, B. Klotz, Interface material mixing formed by the deposition of copper on aluminum by means of the cold spray process, J. Therm. Spray Technol. 14 (3) (Sep. 2005) 330-334. https://doi.org/10.1361/105996305X59332
  16. M. Hassani-Gangaraj, D. Veysset, K.A. Nelson, C.A. Schuh, Supersonic impact of metallic micro-particles, in: Proceedings of the 2006 ITSC, ASM, Seattle, 2016. ArXiv161208081.
  17. T. Stoltenhoff, F. Zimmermann, LOXPlate$^{(R)}$ coatings for aluminum aerospace components exposed to high dynamic stresses, Praxair Surface Technologies GmbH, Ratingen, Germany, 2012.
  18. R. Maev, V. Leshchynsky, A. Papyrin, Structure formation of Ni-based composite coatings during low pressure gas dynamic spraying, in: Proceedings of the 2006 International Thermal Spray Conference, 2006.
  19. N. Bay, Cold Welding. Part 1: Characteristics, Bonding Mechanisms, Bond Strength, 1986.
  20. J. Vlcek, L. Gimeno, H. Huber, E. Lugscheider, A systematic approach to material eligibility for the cold-spray process, J. Therm. Spray Technol. 14 (1) (2005) 125-133. https://doi.org/10.1361/10599630522738
  21. C. Duriez, T. Dupont, B. Schmet, F. Enoch, Zircaloy-4 and M5$^{(R)}$ high temperature oxidation and nitriding in air, J. Nucl. Mater. 380 (1-3) (Oct. 2008) 30-45. https://doi.org/10.1016/j.jnucmat.2008.07.002
  22. R.E. Pawel, J.V. Cathcart, R.A. McKee, The kinetics of oxidation of Zircaloy-4 in steam at high temperatures, J. Electrochem. Soc. 126 (7) (Jul. 1979) 1105-1111. https://doi.org/10.1149/1.2129227
  23. R.L. Williamson, et al., Multidimensional multiphysics simulation of nuclear fuel behavior, J. Nucl. Mater. 423 (1-3) (Apr. 2012) 149-163. https://doi.org/10.1016/j.jnucmat.2012.01.012
  24. J. Hales, et al., BISON Theory Manual the Equations behind Nuclear Fuel Analysis, Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2016.
  25. P.E. Armstrong, H.L. Brown, Dynamic Young's modulus measurements above 1000 C on some pure polycrystalline metals and commercial graphites, Trans. Aime 230 (1964) no. LADC-6100.
  26. M. Wagih, Y. Che, K. Shirvan, Fuel performance of multi-layered zirconium based accident tolerant fuel cladding, in: ICAPP, 2017.

피인용 문헌

  1. Oxidation behavior of RF magnetron sputtered Cr-SiC-Cr composites coating on zircaloy fuel cladding vol.6, pp.9, 2018, https://doi.org/10.1088/2053-1591/ab31e1
  2. Cracking of Cr-coated accident-tolerant fuel during normal operation and under power-ramping conditions vol.353, pp.None, 2018, https://doi.org/10.1016/j.nucengdes.2019.110275
  3. High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environments vol.526, pp.None, 2019, https://doi.org/10.1016/j.jnucmat.2019.151737
  4. Characterization of PVD Cr, CrN, and TiN coatings on SiC vol.527, pp.None, 2018, https://doi.org/10.1016/j.jnucmat.2019.151781
  5. Analysis of Interface Fracture of Cold-Sprayed Coatings Due to Thermal Cycling vol.29, pp.1, 2018, https://doi.org/10.1007/s11666-019-00942-5
  6. System code evaluation of near-term accident tolerant claddings during boiling water reactor short-term and long-term station blackout accidents vol.356, pp.None, 2018, https://doi.org/10.1016/j.nucengdes.2019.110362
  7. Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings by coupling digital image correlation and acoustic emission vol.774, pp.None, 2020, https://doi.org/10.1016/j.msea.2019.138850
  8. Implications of accident tolerant fuels on thermal-hydraulic research vol.358, pp.None, 2020, https://doi.org/10.1016/j.nucengdes.2019.110432
  9. Effectiveness of Cr-Coated Zr-Alloy Clad in Delaying Fuel Degradation for a PWR During a Station Blackout Event vol.206, pp.3, 2018, https://doi.org/10.1080/00295450.2019.1649566
  10. Development and testing of multicomponent fuel cladding with enhanced accidental performance vol.52, pp.3, 2018, https://doi.org/10.1016/j.net.2019.08.015
  11. Physically Based Finite Element Modeling Method to Predict Metallic Bonding in Cold Spray vol.29, pp.4, 2020, https://doi.org/10.1007/s11666-020-01000-1
  12. Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux vol.362, pp.None, 2018, https://doi.org/10.1016/j.nucengdes.2020.110581
  13. Effect of surface characteristics and environmental aging on wetting of Cr-coated Zircaloy-4 accident tolerant fuel cladding material vol.535, pp.None, 2018, https://doi.org/10.1016/j.jnucmat.2020.152163
  14. Quantification of the effect of Cr-coated-Zircaloy cladding during a short term station black out vol.363, pp.None, 2020, https://doi.org/10.1016/j.nucengdes.2020.110678
  15. SEM and EBSD Characterization of Cold-Sprayed Chromium Coatings on Zircaloy-4 vol.26, pp.suppl2, 2020, https://doi.org/10.1017/s1431927620014543
  16. Risk-Informed Safety Analysis for Accident Tolerant Fuels vol.194, pp.8, 2018, https://doi.org/10.1080/00295639.2020.1732699
  17. Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials vol.10, pp.9, 2018, https://doi.org/10.3390/coatings10090808
  18. Pellet-cladding mechanical interaction analysis of Cr-coated Zircaloy cladding vol.367, pp.None, 2018, https://doi.org/10.1016/j.nucengdes.2020.110792
  19. High Temperature Anti-Oxidation Behavior and Mechanical Property of Radio Frequency Magnetron Sputtered Cr Coating vol.10, pp.11, 2018, https://doi.org/10.3390/met10111509
  20. Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4 vol.541, pp.None, 2018, https://doi.org/10.1016/j.jnucmat.2020.152420
  21. Irradiation-induced swelling of pure chromium with 5 MeV Fe ions in the temperature range 450–650 °C vol.543, pp.None, 2018, https://doi.org/10.1016/j.jnucmat.2020.152585
  22. Protection of Zr Alloy under High-Temperature Air Oxidation: A Multilayer Coating Approach vol.11, pp.2, 2018, https://doi.org/10.3390/coatings11020227
  23. High-Temperature Oxidation of Cr-Coated Resistance Upset Welds Made from E110 Alloy vol.11, pp.5, 2021, https://doi.org/10.3390/coatings11050577
  24. ZrN Phase Formation, Hardening and Nitrogen Diffusion Kinetics in Plasma Nitrided Zircaloy-4 vol.14, pp.13, 2018, https://doi.org/10.3390/ma14133572
  25. BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms vol.207, pp.7, 2018, https://doi.org/10.1080/00295450.2020.1836940
  26. Study of Coatings Formed on Zirconium Alloy by Plasma Electrolytic Oxidation in Electrolyte with Submicron Yttria Powder Additives vol.11, pp.9, 2018, https://doi.org/10.3390/met11091392
  27. Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm vol.207, pp.10, 2018, https://doi.org/10.1080/00295450.2020.1826272
  28. Corrosion Behavior of Chromium Coated Zy-4 Cladding under CANDU Primary Circuit Conditions vol.11, pp.11, 2018, https://doi.org/10.3390/coatings11111417
  29. Effects of oxidation and inter-diffusion on the fracture mechanisms of Cr-coated Zry-4 alloys: An in situ three-point bending study vol.212, pp.None, 2018, https://doi.org/10.1016/j.matdes.2021.110168
  30. Grid-to-rod fretting wear study of SiC/SiC composite accident-tolerant fuel claddings using an autoclave fretting bench test vol.488, pp.None, 2018, https://doi.org/10.1016/j.wear.2021.204172
  31. High-temperature oxidation of Cr-coated laser beam welds made from E110 zirconium alloy vol.195, pp.None, 2018, https://doi.org/10.1016/j.corsci.2021.110018
  32. Review on chromium coated zirconium alloy accident tolerant fuel cladding vol.895, pp.p1, 2018, https://doi.org/10.1016/j.jallcom.2021.162450