journal article·2024-04

Elucidating changes in thermal creep strain rate of Cr-coated Zr-Nb alloy Accident Tolerant Fuel (ATF) cladding via experiment and mechanical analysis

Jinsu Kim, Chung Yong Lee, Hyuntaek Rho, Dongju Kim, Jeonghyeon Lee, Hun Jang, Youho Lee

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Abstract

Remarkable decrease in creep strain rate (86% decrease) was observed for Zr-1.1Nb alloy cladding coated with a thin Cr layer (16.8μm) compared to uncoated cladding in the present experiment at 380°C. The structural analysis with the in-house code and FEM analysis showed good agreement with the experimental results, demonstrating that the creep strain rate reduction was primarily occurred by mechanical cause. Cr coating layer induces extra compressive stress on the underlying cladding due to the strain compatibility, reducing the tensile stress level on the underlying cladding and thereby resulting in a decreased creep strain rate. This suggests the coating layer has non-negligible impact on the overall mechanical behavior of the underlying cladding despite of its significantly thin thickness. In addition, the XRD analysis found that the Cr coating layer has high compressive residual stress that also impedes the creep deformation of the underlying cladding. However, if the residual stress within the coating layer is limited or absent, the creep deformation will not be dramatically reduced. Inclusion of appreciable creep or plastic deformation of Cr coating led to the use of unrealistically high elastic modulus to match the experimental results. This result implies that creep or plastic deformation in the Cr coating layer is likely to be absent or negligible in the tested conditions. The magnitude of irradiation creep is markedly greater than that of thermal creep, and is less sensitive to the changes in stress which is induced by coating. Therefore, the extent of changes in creep strain rate in the reactor environment is anticipated to be less than that of an out-of-pile thermal creep experiments. It can be estimated that the creep strain rate will be decreased by 10–20% with Cr-coated cladding (Cr-thickness of 10μm - 20μm) at BOL.
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Research context

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

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (44)

Show source-provided references
1. Accident tolerant fuel cladding development: promise, status, and challenges10.1016/j.jnucmat.2017.12.043 ↗
2. Review on chromium coated zirconium alloy accident tolerant fuel cladding10.1016/j.jallcom.2021.162450 ↗
3. Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors10.1016/j.jnucmat.2019.02.018 ↗
4. Microstructure, corrosion resistance and oxidation behavior of Cr-coatings on Zircaloy-4 prepared by vacuum arc plasma deposition10.1016/j.corsci.2019.06.029 ↗
5. High temperature steam oxidation of chromium-coated zirconium-based alloys: kinetics and process10.1016/j.corsci.2020.108537 ↗
6. Post-LOCA ductility of Cr-coated cladding and its embrittlement limit10.1016/j.jnucmat.2021.153354 ↗
7. Development and testing of multicomponent fuel cladding with enhanced accidental performance10.1016/j.net.2019.08.015 ↗
8. Assessment at CEA of coated nuclear fuel cladding for LWRs with increased margins in LOCA and beyond LOCA conditions
9. Bischoff · 2016
10. 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 ↗
11. Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-410.1016/j.jnucmat.2020.152420 ↗
12. Behavior under LOCA conditions of enhanced accident tolerant chromium coated zircaloy-4 claddings
13. Behavior of chromium coated M5 claddings under LOCA conditions
14. Behavior of chromium coated M5 claddings upon thermal ramp tests under internal pressure (loss-of-coolant accident conditions
15. Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions10.1016/j.jnucmat.2016.10.021 ↗
16. Numerical investigation of ballooning and burst for chromium coated zircaloy cladding10.1016/j.nucengdes.2021.111420 ↗
17. Chromium-coated cladding analysis under simulated LOCA burst conditions10.1016/j.anucene.2022.109275 ↗
18. Semi-integral LOCA test of cold-spray chromium coated zircaloy-4 accident tolerant fuel cladding10.1016/j.jnucmat.2021.152940 ↗
19. Experimental investigation of cold-spray Cr-coated cladding during normal and accident conditions
20. Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings10.1016/j.anucene.2018.06.001 ↗
21. Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance10.1016/j.net.2017.12.011 ↗
22. Mechanical analysis of surface-coated zircaloy cladding10.1016/j.net.2017.03.012 ↗
23. Rho · 2023
24. Sim · 2023
25. Oxidation of zircaloy cladding in air10.1016/0022-3115(86)90194-7 ↗
26. The role of space charge in the oxidation of Zircaloy-4 between 350 and 450°C in air10.1016/0022-3115(93)90149-S ↗
27. Geelhood · 2011
28. Thermal creep of Zircaloy-4 cladding under internal pressure10.1080/18811248.1987.9735783 ↗
29. Theory of creep under the action of combined stresses with applications to high temperature machinery
30. Analysis of thick-walled orthotropic cylinder in the theory of creep10.1143/JPSJ.27.1655 ↗
31. Large strain creep analysis of thick-walled cylinders10.1016/0020-7462(74)90004-3 ↗
32. Luscher · 2010
33. In-situ study on the tensile behavior of Cr-coated zircaloy for accident tolerant fuel claddings10.1016/j.surfcoat.2020.125747 ↗
34. Measurement of local mechanical properties for Cr-coated accident tolerant fuel cladding10.1016/j.jnucmat.2023.154407 ↗
35. Effect of bilayer period on properties of Cr/CrN multilayer coatings produced by laser ablation10.1016/j.surfcoat.2007.12.036 ↗
36. Characterisation of chromium nitride films produced by PVD techniques10.1016/S0040-6090(01)01498-5 ↗
37. A method for elastic modulus measurements of magnetron sputtered thin films dedicated to mechanical applications10.1016/0040-6090(95)06921-6 ↗
38. Mechanical damage of hard chromium coatings on 416 stainless steel10.1016/j.engfailanal.2016.04.011 ↗
39. Effects of the ratio of hardness to Young's modulus on the friction and wear behavior of bilayer coatings10.1063/1.1811377 ↗
40. X-ray diffraction residual stress techniques
41. Residual stress measurement by X-ray diffraction
42. Mechanical behaviour of hard chromium deposited from a trivalent chromium bath10.3390/coatings12030354 ↗
43. Mechanical and thermomechanical properties of commercially pure chromium and chromium alloys10.1016/S0022-3115(01)00745-0 ↗
44. Creep strength of Zircaloy-4 cladding depending on applied stress and annealing temperature10.1016/S0022-3115(02)00917-0 ↗