journal article·2025-05Open access

Semi-integral LOCA testing of Cr-coated Optimized ZIRLOTM claddings

Ioannis Alakiozidis, Marc Lopes Nunes de Sousa, Axel Gauthier, Callum Hunt, Mia Maric, Antoine Ambard, Zaheen Shah, Philipp Frankel

Abstract

• Unique thermomechanical LOCA testing in a single apparatus. • Cr-coated claddings exhibited increased burst temperatures. • Cr-coated claddings exhibited decreased strain-to-burst and ballooning. • Cr-coated claddings exhibited increased resistance to post-quenching embrittlement. • More conservative benefits from coatings when multiple LOCA effects are considered. Chromium (Cr)-coatings on zirconium-(Zr) based claddings have emerged as a promising short-term solution to enhance the accident tolerance of fuel assemblies in pressurised water reactors (PWRs) during loss-of-coolant accidents (LOCAs). In this study, we tested a large number (36 rods in total, each 30cm long) of uncoated and Cr-coated Optimized ZIRLO TM claddings under thermomechanical conditions that closely resemble a real LOCA. A unique experimental apparatus was employed to integrate multiple LOCA effects into a single test sequence, enabling a more accurate prediction of the performance of Cr-coatings and degradation mechanisms of the coated claddings. More specifically, the test sequence included: i) thermal ramping from 350–1200°C under varying internal pressures and heating rates in flowing steam; ii) isothermal steam oxidation at 1200°C for different durations; ii) cooling to 700°C followed by water quenching to 135°C; iv) partial-axial constraint at 135°C with load hold of 540N for 20s. Various characterisation techniques, including optical and scanning electron microscopy (SEM), 3D laser scanning, electron backscattered diffraction (EBSD), hardness testing and hydrogen analysis, were used to characterise the post-LOCA cladding microstructures. We found that Cr-coatings increased the burst temperature of uncoated claddings by ∼ 25–150°C and reduced the strain-to-burst and cladding deformation within 20 mm away from the burst opening. The magnitude of these improvements depended on the initial testing conditions and were more pronounced for the helium-propelled cold spray (HCS) coating, while less pronounced for the nitrogen-propelled CS (NCS) and physical vapour deposition (PVD) coatings. Additionally, we found that Cr-coatings increased the time threshold before significant cladding embrittlement by ∼100–555s compared to uncoated claddings. Finally, we concluded that when multiple LOCA effects are considered, predictions of additional coping time during a LOCA provided by the Cr-coatings are more conservative compared to single-factor tests.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies

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References (78)

Show source-provided references
1. Review on chromium coated zirconium alloy accident tolerant fuel cladding10.1016/j.jallcom.2021.162450 ↗
2. Accident tolerant fuels for LWRs: A perspective10.1016/j.jnucmat.2013.12.005 ↗
3. Chapman · 1979
4. A State-of-the-Art Review of past programs devoted to fuel behavior under LOCA conditions
5. Cladding burst behavior of Fe-based alloys under LOCA10.1016/j.jnucmat.2015.12.018 ↗
6. Accident tolerant fuel cladding development: Promise, status, and challenges10.1016/j.jnucmat.2017.12.043 ↗
7. Secondary hydriding during LOCA – Results from the QUENCH-L0 test10.1016/j.jnucmat.2011.11.045 ↗
8. Contribution to the understanding of brittle fracture conditions of zirconium alloy fuel cladding tubes during LOCA transient10.1016/j.jnucmat.2019.151815 ↗
9. Protective coatings on zirconium-based alloys as accident-Tolerant fuel (ATF) claddings10.1515/corrrev-2017-0010 ↗
10. Application and development progress of cr-based surface coatings in nuclear fuel element: I. Selection, preparation, and characteristics of coating materials
11. Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors10.1016/j.jnucmat.2019.02.018 ↗
12. Development of surface modified Zr cladding by coating technology for ATF
13. Application and development progress of Cr-based surface coating in nuclear fuel elements: II. current status and shortcomings of performance studies10.3390/coatings10090835 ↗
14. High-temperature oxidation and quenching of chromium-coated zirconium alloy ATF cladding tubes with and w/o pre-damage10.1016/j.jnucmat.2021.153470 ↗
15. Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-410.1016/j.jnucmat.2020.152420 ↗
16. Cr-coated cladding development at Framatome
17. Measurement of local mechanical properties for Cr-coated accident tolerant fuel cladding10.1016/j.jnucmat.2023.154407 ↗
18. Experimental behavior of chromium-based coatings
19. Construction of Cr coatings with different columnar structure on Zircaloy-4 alloys to optimize the high-temperature steam oxidation behavior for accident tolerant fuel claddings10.1016/j.jallcom.2023.169385 ↗
20. Construction of chromium coatings with (200) preferred orientation and exploration the high-temperature steam oxidation properties10.1016/j.jnucmat.2022.153660 ↗
21. Corrosion behavior of Cr-coated zirconium alloy cladding in LiOH/H3BO3-containing water at 360 °C10.1016/j.corsci.2023.111386 ↗
22. In situ X-ray computed micro-tomography imaging of failure processes in Cr-coated Zircaloy nuclear fuel cladding materials10.1016/j.matdes.2023.112373 ↗
23. A systematic study of the oxidation behavior of Cr coatings on Zry4 substrates in high temperature steam environment10.1016/j.corsci.2020.108826 ↗
24. An interesting oxidation phenomenon of Cr coatings on Zry-4 substrates in high temperature steam environment10.1016/j.corsci.2019.05.017 ↗
25. Burst and oxidation behavior of Cr-coated Zirlo during simulated LOCA testing10.1016/j.jnucmat.2022.153679 ↗
26. Oxidation behavior of Cr-coated zirconium alloy cladding in high-temperature steam above 1200 °C10.1038/s41529-021-00155-8 ↗
27. Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance10.1016/j.net.2017.12.011 ↗
28. Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding10.1016/j.jnucmat.2019.03.039 ↗
29. Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors10.1007/s11837-017-2643-9 ↗
30. Shahin · 2018 · 1
31. Semi-integral LOCA test of cold-spray chromium coated zircaloy-4 accident tolerant fuel cladding10.1016/j.jnucmat.2021.152940 ↗
32. Performance and evolution of cold spray Cr-coated optimized ZIRLO™ claddings under simulated loss-of-coolant accident conditions10.1016/j.jnucmat.2023.154268 ↗
33. High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environments10.1016/j.jnucmat.2019.151737 ↗
34. Characterization of as-deposited cold sprayed Cr-coating on Optimized ZIRLO™ claddings10.1016/j.jnucmat.2021.152892 ↗
35. Oxidation and quench behavior of cold spraying Cr-coated zircaloy fuel cladding under severe accident scenarios
36. Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions10.1016/j.jnucmat.2016.10.021 ↗
37. Behavior under LOCA conditions of enhanced accident tolerant chromium coated zircaloy-4 claddings
38. Burst and oxidation behavior of Cr-coated Zirlo during simulated LOCA testing10.1016/j.jnucmat.2022.153679 ↗
39. Coated cladding behavior during high-temperature transients10.14311/APP.2019.24.0009 ↗
40. Steam oxidation of Cr-coated zirconium alloy claddings at 1200 °C: Kinetics transition and failure mechanism of Cr coatings10.1016/j.jnucmat.2023.154684 ↗
41. High temperature steam oxidation of chromium-coated zirconium-based alloys: kinetics and process10.1016/j.corsci.2020.108537 ↗
42. Post-LOCA ductility of Cr-coated cladding and its embrittlement limit10.1016/j.jnucmat.2021.153354 ↗
43. Evaluation of Equivalent Cladding Reacted parameters of Cr-coated claddings oxidized in steam at 1200°C in relation with oxygen diffusion/partitioning and post-quench ductility10.1016/j.jnucmat.2020.152106 ↗
44. Cold spraying – a materials perspective10.1016/j.actamat.2016.06.034 ↗
45. Characterization of as-deposited cold sprayed Cr-coating on optimized ZIRLO TM claddings10.1016/j.jnucmat.2021.152892 ↗
46. Microstructure and mechanical performance of cold spray Cr coatings10.1016/j.jnucmat.2024.155492 ↗
47. Quantifying cracking and strain localisation in a cold spray chromium coating on a zirconium alloy substrate under tensile loading at room temperature10.1016/j.jnucmat.2024.154899 ↗
48. High temperature creep model development using in-situ 3-D DIC techniques during a simulated LOCA transient10.1016/j.anucene.2023.110012 ↗
49. Effects of alpha-beta transformation on high temperature (LOCA) creep behavior of Zr-alloys
50. Powers · 1980
51. Thieurmel · 2018
52. Cathcart · 1977
53. Chapman · 1978
54. Chromium-coated cladding analysis under simulated LOCA burst conditions10.1016/j.anucene.2022.109275 ↗
55. Evaluation of air oxidation and internal stresses induced by quenching of partially Cr-coated and uncoated optimized ZIRLO part I: materials characterization10.1016/j.jallcom.2023.171658 ↗
56. Chung · 1978
57. Effect of quenching rate on the β-to-α phase transformation structure in zirconium alloy10.1016/S0022-3115(03)00323-4 ↗
58. Study of oxide and α-Zr (O) growth kinetics from high temperature steam oxidation of Zircaloy-4 cladding10.1016/j.jnucmat.2015.10.012 ↗
59. Effects of Cr/Zircaloy-4 coating qualities for enhanced accident tolerant fuel cladding10.1016/j.anucene.2023.109799 ↗
60. Neumann · 2011
61. Baker Jr · 1962
62. Billone · 2008
63. Hydrogen content, preoxidation, and cooling scenario effects on post-quench microstructure and mechanical properties of Zircaloy-4 and M5 alloys in LOCA conditions10.1520/JAI101116 ↗
64. Hydride precipitation, fracture and plasticity mechanisms in pure zirconium and Zircaloy-4 at temperatures typical for the postulated loss-of-coolant accident10.1016/j.nucengdes.2016.03.024 ↗
65. Brachet · J. Nuclear Mater. · 2017 · 488 · 26710.1016/j.jnucmat.2017.03.009 ↗
66. QUENCH-LOCA program at KIT on secondary hydriding and results of the commissioning bundle test QUENCH-L010.1016/j.nucengdes.2012.10.024 ↗
67. Neutron imaging investigations of the secondary hydriding of nuclear fuel cladding alloys during loss of coolant accidents10.1016/j.phpro.2015.07.061 ↗
68. The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts10.1016/j.jnucmat.2022.154152 ↗
69. Effects of Cr/Zircaloy-4 coating qualities for enhanced accident tolerant fuel cladding10.1016/j.anucene.2023.109799 ↗
70. Effects of internal pressure and heating rate on the burst behaviors of Cr-coated cladding during simulated LOCA testing10.1016/j.anucene.2024.110548 ↗
71. Powers · 1979
72. Numerical investigation of ballooning and burst for chromium coated zircaloy cladding10.1016/j.nucengdes.2021.111420 ↗
73. Seibert · 2024
74. Billone · 2002
75. Flanagan · 2012
76. M. Grosse, J. Stuckert, and M. Steinbrück, "Parameters influencing the hydrogen concentration and distribution in cladding tubes after LOCA: results of bundle-scale experiments and modeling," (in english), 2014.
77. Finite element analysis of the grain size effect on diffusion in polycrystalline materials10.1016/j.commatsci.2014.07.026 ↗
78. Oxidation kinetics of Cr-coated zirconium alloy: Effect of coating thickness and microstructure10.1016/j.corsci.2020.108883 ↗