Evolution of Microstructure and Surface Characteristics of FeCrAl alloys when Subjected to Flow Boiling Testing
Source abstract
Abstract
ABSTRACT FeCrAl alloys are candidate materials for manufacturing accident-tolerant fuel (ATF) cladding intended for light water reactors to increase fuel reliability and safety during design-basis and beyond-design-basis accident scenarios. The evolution of the materials' surface characteristics, microstructure, and mechanical properties when exposed to the Critical Heat Flux (CHF) in flow boiling testing is crucial for safety analysis while providing insights into their thermal-hydraulic performance in nuclear reactors. After CHF, the surface chemistry of two FeCrAl alloys, APMT and C26M, was studied to understand their evolution at the early stage of high-temperature excursions in short time periods. The results indicated a thin layer composed of oxides and hydroxides of Al, Cr, and Fe with varying proportions at different depths in the layer, as indicated by X-ray photoelectron spectroscopy (XPS) and depth profiling. The cross-sections prepared by focused ion beam (FIB) revealed the growth of an oxide layer, in the range of 90-180 nm thick, on the alloys' surfaces. The evolution of the materials' surface chemistry also led to a noticeable post CHF excursion increase in their wettability, with a slight increase in roughness. The investigation of the materials' mechanical properties indicated a modest increase in hardness by 10-15% as well as an increase in their yield strength, as evidenced by the microindentation and ring compression tests conducted before and after CHF testing. Scanning electron Microscopy (SEM) and X-ray diffraction (XRD) were used to investigate microstructural features of the materials and their changes after CHF treatment.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (100+)
Show source-provided references
1. Accident tolerant fuels for LWRs: A perspective10.1016/j.jnucmat.2013.12.005 ↗
2. Accident tolerant fuel cladding development: Promise, status, and challenges10.1016/j.jnucmat.2017.12.043 ↗
3. Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure10.1016/j.jnucmat.2012.05.007 ↗
4. Alloy Selection for Accident Tolerant Fuel Cladding in Commercial Light Water Reactors
5. Pint · Material Selection for Accident Tolerant Fuel Cladding, Metall. Mater. Trans. E. · 2015 · 2 · 190
6. KAERI's Development of LWR Accident-Tolerant Fuel10.13182/NT13-89 ↗
7. On-going studies at CEA on chromium coated zirconium based nuclear fuel claddings for enhanced Accident Tolerant LWRs Fuel
8. Development Status of Accident-tolerant Fuel for Light Water Reactors in Korea10.1016/j.net.2015.11.011 ↗
9. Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding10.1016/j.net.2015.12.003 ↗
10. Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys10.1016/j.jnucmat.2015.06.023 ↗
11. Enchanced high-temperature performances of SiC/SiC composites by high densification and crystalline structure10.1016/j.compscitech.2010.11.026 ↗
12. Characterization of SiC-SiC composites for accident tolerant fuel cladding10.1016/j.jnucmat.2015.08.020 ↗
13. Rebak · 2020
14. K. Barrett, S. Bragg-Sitton, D. Galicki, Advanced LWR Nuclear Fuel Cladding System Development Trade-off Study, Idaho 83415 INL/EXT-12-27090. (2012) 1–34. doi:10.2172/1057698.10.2172/1057698 ↗
15. Protective coatings on zirconium-based alloys as accident-Tolerant fuel (ATF) claddings10.1515/corrrev-2017-0010 ↗
16. Development of Cold Spray Coatings for Accident-Tolerant Fuel Cladding in Light Water Reactors10.1007/s11837-017-2643-9 ↗
17. Effect of roughness of substrate and sputtering power on the properties of TiN coatings deposited by magnetron sputtering for ATF10.1016/j.jnucmat.2018.07.011 ↗
18. Development of Surface Modified Zr Cladding by Coating Technology for ATF
19. Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air10.1016/j.jnucmat.2015.06.016 ↗
20. Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating10.1016/j.jnucmat.2015.06.030 ↗
21. On Coating Techniques for Surface Protection: A Review
22. Molybdenum silicide based materials and their properties10.1361/105994999770346837 ↗
23. Nickel-chromium (Ni–Cr) coatings deposited by magnetron sputtering for accident tolerant nuclear fuel claddings10.1016/j.surfcoat.2019.04.057 ↗
24. J. Krejci, M. Sevecek, DEVELOPMENT OF CHROMIUM AND CHROMIUM NITRIDE COATED CLADDING 2017 Water Reactor Fuel Performance Meeting, (2017).
25. Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings10.1016/j.anucene.2018.06.001 ↗
26. Deposition, characterization and performance evaluation of ceramic coatings on metallic substrates for supercritical water-cooled reactors10.1016/j.surfcoat.2010.12.017 ↗
27. HRTEM and chemical study of an ion-irradiated chromium/zircaloy-4 interface10.1016/j.jnucmat.2018.01.029 ↗
28. High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings10.1016/j.surfcoat.2015.09.022 ↗
29. Experimental investigation of cold-spray chromium cladding
30. Fatigue Behavior of Cold Spray - Coated Accident Tolerant
31. Behavior of Chromium Coated M5 Claddings under LOCA Conditions, 2017 Water React. Fuel Perform. Meet. 2017 Water React. Fuel Perform
32. Development of Surface Coatings for Enhanced Accident Tolerant Fuel
33. H.O. Behavior, O.F.C. Zirconium, H. Kim, I. Kim, Y. Jung, D. Park, J. Park, Y. Koo, I. Introduction, HIGH-TEMPERATURE OXIDATION BEHAVIOR OF CR-COATED ZIRCONIUM ALLOY, (2013) 842–846.
34. Mechanical and Chemical Properties of PVD and Cold Spray Cr-coatings on Zircaloy-410.1016/j.jnucmat.2020.152420 ↗
35. Effect of surface characteristics and environmental aging on wetting of Cr-coated Zircaloy-4 accident tolerant fuel cladding material10.1016/j.jnucmat.2020.152163 ↗
36. CEA studies on advanced nuclear fuel claddings for enhanced Accident Tolerant LWRs Fuel(LOCA and beyond LOCA conditions), Fontevraud 8 - Contribution of Materials Investigations and Operating Experience to LWRs’ Safety
37. Assessment at CEA of coated nuclear fuel cladding for LWRS with increased margins in loca and beyond loca conditions
38. Cr-coated Zr-4 alloy prepared by electroplating and its in situ He+ irradiation behavior10.1016/j.jnucmat.2020.152240 ↗
39. High energy heavy ion irradiation of chromium films10.1016/0042-207X(94)00081-6 ↗
40. Microstructure investigation of Cr and Cr alloys irradiated with heavy ions10.1016/0022-3115(95)00066-6 ↗
41. Mechanical analysis of surface-coated zircaloy cladding10.1016/j.net.2017.03.012 ↗
42. Accident tolerant fecral fuel cladding: current status towards commercialization
43. STEAM OXIDATION, BURST AND CRITICAL HEAT FLUX TESTING OF COMMERCIAL FECRAL CLADDING B. A. Pint, L. A. Baldesberger and K. A. Kane, (2019) 311–316.
44. Steam oxidation behavior of fecral cladding
45. Versatile Oxide Films Protect FeCrAl Alloys Under Normal Operation and Accident Conditions in Light Water Power Reactors10.1007/s11837-017-2705-z ↗
46. A study of the oxidation of FeCrAl alloy in pressurized water and high-temperature steam environment10.1016/j.corsci.2015.02.027 ↗
47. Influence of composition and heating schedules on compatibility of FeCrAl alloys with high-temperature steam10.1016/j.jnucmat.2018.09.026 ↗
48. Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys10.1016/j.jnucmat.2017.03.038 ↗
49. Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations10.1016/j.jnucmat.2018.03.002 ↗
50. ORNL, Handbook on the Material Properties of FeCrAl alloys for Nuclear Power Production Applications, 2017.
51. K.G. Field, M. Snead, Y. Yamamoto, B.A. Pint, K.A. Terrani, Materials properties of FeCrAl alloys for nuclear power production applications, (2017) 39.10.2172/1474581 ↗
52. Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors10.1016/j.jnucmat.2015.10.019 ↗
53. Microstructure and high temperature mechanical properties of as-cast FeCrAl alloys10.1016/j.msea.2018.04.039 ↗
54. Preliminary thermal hydraulic analysis of various accident tolerant fuels and claddings for control rod ejection accidents in LWRs10.1016/j.nucengdes.2018.03.007 ↗
55. Investigations on the Thermal-hydraulic Behavior of Accident Tolerant Fuel Cladding Materials
56. Survey of Thermal-Fluids Evaluation and Confirmatory Experimental Validation Requirements of Accident Tolerant Cladding Concepts with Focus on Boiling Heat Transfer Characteristics
57. B. Zohuri, N. Fathi, Thermal-Hydraulic Analysis of Nuclear Reactors, 2015. doi:10.1007/978-3-319-17434-1.10.1007/978-3-319-17434-1 ↗
58. A Theoretical Model to Predict Pool Boiling CHF Incorporating Effects of Contact Angle and Orientation10.1115/1.1409265 ↗
59. Effect of surface roughness on pool boiling heat transfer at a heated surface having moderate wettability10.1016/j.ijheatmasstransfer.2016.05.067 ↗
60. W.M. Rohsenow, A Method of Correlating Heat Transfer Data for Surface Boiling of Liquids, Trans. ASME. Vol. 74 (n.d.) 969–976.10.1115/1.4015984 ↗
61. Surface wettability effects on critical heat flux of boiling heat transfer using nanoparticle coatings10.1016/j.ijheatmasstransfer.2012.03.003 ↗
62. N. Zuber, Hydrodynamic Aspects Of Boiling Heat Transfer (Thesis), (1959). doi:10.2172/4175511.10.2172/4175511 ↗
63. Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux10.1016/j.nucengdes.2020.110581 ↗
64. Capillary wicking effect of a Cr-sputtered superhydrophilic surface on enhancement of pool boiling critical heat flux10.1016/j.ijheatmasstransfer.2017.05.055 ↗
65. Enhanced pool boiling critical heat flux with a FeCrAl layer fabricated by DC sputtering10.1016/j.ijheatmasstransfer.2016.06.077 ↗
66. Chromia coating with nanofluid deposition and sputtering for accident tolerance, CHF enhancement10.1016/j.ijheatmasstransfer.2017.11.060 ↗
67. Critical heat flux for SiC- and Cr-coated plates under atmospheric condition10.1016/j.anucene.2014.09.046 ↗
68. Oxidation effect on pool boiling critical heat flux enhancement of Cr-coated surface for accident-tolerant fuel cladding application10.1016/j.ijheatmasstransfer.2019.118655 ↗
69. Surface wettability and pool boiling Critical Heat Flux of Accident Tolerant Fuel cladding-FeCrAl alloys10.1016/j.nucengdes.2018.08.024 ↗
70. Experimental study of saturated pool boiling heat transfer with FeCrAl- and Cr-layered vertical tubes under atmospheric pressure10.1016/j.ijheatmasstransfer.2018.09.013 ↗
71. Evaluation of critical heat flux of ATF candidate coating materials in pool boiling10.1016/j.nucengdes.2019.110166 ↗
72. Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel10.1016/j.ijheatmasstransfer.2018.11.141 ↗
73. Quenching experiment on Cr-alloy-coated cladding for accident-tolerant fuel in water pool under low and high subcooling conditions10.1016/j.nucengdes.2019.03.017 ↗
74. Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for Accident Tolerant Fuel (ATF) materials
75. Elward · 2020
76. ASTM International, Astm D 5725, 99 (1999) 1–7.
77. R. Umretiya, D. Ginestro, S. Bilbao y Leon, J. Rojas, B. Elward, M. Anderson, R.B. Rebak, Surface characteristics of accident tolerant fuels cladding and their potential impact in critical heat flux, in: 18th Int. Top. Meet. Nucl. React. Therm. Hydraul. NURETH 2019, 2019.
78. Flynn · International Standard · 2003
79. Standard Practice for Instrumented Indentation Testing
80. Roughness parameters10.1016/S0924-0136(02)00060-2 ↗
81. Definitions for hydrophilicity, hydrophobicity, and superhydrophobicity: Getting the basics right10.1021/jz402762h ↗
82. Angle · 2015 · 1
83. K.J. Kubiak, M.C.T. Wilson, T.G. Mathia, P. Carval, Wettability versus roughness of engineering surfaces, 271 (2011) 523–528.10.1016/j.wear.2010.03.029 ↗
84. Effect of oxidation and fractal surface roughness on the wettability and critical heat flux of class-peened zirconium alloy tubes
85. Wettability versus roughness: Multi-scales approach10.1016/j.triboint.2014.07.002 ↗
86. Y.J. Lim, Y. Oshida, C.J. Andres, M.T. Barco, Surface characterizations of variously treated titanium materials., Int. J. Oral Maxillofac. Implants.16 (n.d.) 333–42. http://www.ncbi.nlm.nih.gov/pubmed/11432653.
87. Comparison of the sputter rates of oxide films relative to the sputter rate of SiO210.1116/1.3456123 ↗
88. X-ray photoelectron spectroscopy of ion beam sputter deposited SiO 2, TiO 2, and Ta 2 O 510.1116/1.572746 ↗
89. Studies of the sputter deposition of carbon, silicon and SiC films10.1016/0040-6090(82)90568-5 ↗
90. Thickness determination of corrosion layers on iron using XPS depth profiling10.17222/mit.2016.180 ↗
91. Sputtering yields of compounds using argon ions10.1088/0022-3727/43/25/253001 ↗
92. X-ray Photoelectron Spectroscopic Studies of Iron Oxides10.1021/ac50019a016 ↗
93. Peak fitting of the chromium 2p XPS spectrum10.1016/0169-4332(95)00168-9 ↗
94. X-ray photoelectron spectroscopy (XPS)10.1002/0470014229.ch22 ↗
95. Investigation of multiplet splitting of Fe 2p XPS spectra and bonding in iron compounds10.1002/sia.1984 ↗
96. Resolving surface chemical states in XPS analysis of first row transition metals, oxides and hydroxides: Cr, Mn, Fe, Co and Ni10.1016/j.apsusc.2010.10.051 ↗
97. Analysis of XPS results of AISI 316L SS electropolished and magnetoelectropolished at varying conditions10.1016/j.surfcoat.2010.02.005 ↗
98. Structure and stability of aluminum hydroxides: A theoretical study10.1021/jp014182a ↗
99. Atmospheric Pressure Plasma Treatment and Following Aging Effect of Chromium Surfaces
100. Microstructural stability of Fe-Cr-Al alloys at 450-550°C10.1016/j.jnucmat.2014.11.101 ↗