Ductile-to-brittle transition behavior and mechanism of Cr-coated Zr-1Nb alloys after 1000–1200 °C steam oxidation
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OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
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References (37)
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1. Out-of-pile performance of surface-modified Zr cladding for accident tolerant fuel in LWRs10.1016/j.jnucmat.2018.07.061 ↗
2. Corrosion of zirconium alloys used for nuclear fuel cladding10.1146/annurev-matsci-070214-020951 ↗
3. Accident tolerant fuels for LWRs: a perspective10.1016/j.jnucmat.2013.12.005 ↗
4. Current status of materials development of nuclear fuel cladding tubes for light water reactors10.1016/j.nucengdes.2017.02.031 ↗
5. Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings10.1515/corrrev-2017-0010 ↗
6. CEA studies on advanced nuclear fuel claddings for enhanced accident tolerant LWRs fuel
7. Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions10.1016/j.jnucmat.2013.09.052 ↗
8. Review on performance of chromium-coated zirconium and its failure mechanisms, front
9. Pellet-cladding mechanical interaction analysis of Cr-coated Zircaloy cladding10.1016/j.nucengdes.2020.110792 ↗
10. High-temperature oxidation of thick Cr coating prepared by arc deposition for accident tolerant fuel claddings10.1016/j.jnucmat.2019.01.039 ↗
11. Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-410.1016/j.jnucmat.2020.152420 ↗
12. Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings by coupling digital image correlation and acoustic emission10.1016/j.msea.2019.138850 ↗
13. Achieving strength-ductility synergy in zirconium via ultra-dense twin-twin networks10.1016/j.actamat.2024.119825 ↗
14. Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors10.1016/j.jnucmat.2019.02.018 ↗
15. High temperature steam oxidation of chromium-coated zirconium-based alloys: kinetics and process10.1016/j.corsci.2020.108537 ↗
16. Systematic investigations on the coating degradation mechanism during the steam oxidation of Cr-coated Zry-4 at 1200°C10.1016/j.corsci.2022.110310 ↗
17. Temperature-time dependence and mechanisms of redox reaction in Cr-coated Zr alloy cladding during steam oxidation at 900–1250 °C10.1016/j.jnucmat.2024.155094 ↗
18. A systematic study of the oxidation behavior of Cr coatings on Zry4 substrates in high temperature steam environment10.1016/j.corsci.2020.108826 ↗
19. An interesting oxidation phenomenon of Cr coatings on zry-4 substrates in high temperature steam environment10.1016/j.corsci.2019.05.017 ↗
20. Investigations of oxidation behavior and establishment of life-cycle model during the steam oxidation of Cr-coated Zry-4 at 1200 °C10.1016/j.corsci.2023.111694 ↗
21. Positive or negative role of preoxidation in the crack arresting of Cr coating for accident tolerant fuel cladding10.1016/j.corsci.2021.109870 ↗
22. Mechanical behavior of a chromium coating on a zirconium alloy substrate at room temperature10.1016/j.jnucmat.2021.153332 ↗
23. Effects of oxidation and inter-diffusion on the fracture mechanisms of Cr-coated Zry-4 alloys: an in situ three-point bending study10.1016/j.matdes.2021.110168 ↗
24. Microstructure, corrosion resistance and oxidation behavior of Cr-coatings on Zircaloy-4 prepared by vacuum arc plasma deposition10.1016/j.corsci.2019.06.029 ↗
25. Billone · 2008 · 946677
26. Hobson · 1972
27. Post-LOCA ductility of Cr-coated cladding and its embrittlement limit10.1016/j.jnucmat.2021.153354 ↗
28. A new cladding embrittlement criterion derived from ring compression tests10.1016/j.nucengdes.2014.03.047 ↗
29. Hache · 2002
30. Steam oxidation of Cr-coated zirconium alloy claddings at 1200°C: kinetics transition and failure mechanism of Cr coatings10.1016/j.jnucmat.2023.154684 ↗
31. Brachet · 2009 · 1505 · 91
32. Study of oxide and α-Zr(O) growth kinetics from high temperature steam oxidation of zircaloy-4 cladding10.1016/j.jnucmat.2015.10.012 ↗
33. Oxygen, hydrogen and main alloying chemical elements partitioning upon alpha-beta phase transformation in zirconium alloys10.4028/www.scientific.net/SSP.172-174.753 ↗
34. Investigations of the microstructure and mechanical properties of prior-β structure as a function of the oxygen content in two zirconium alloys10.1520/JAI101119 ↗
35. Brachet · 2023 · 433
36. 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 ↗
37. Diffusion of chromium of Cr-coated Zircaloy accident tolerant fuel cladding: model development and experimental validation10.1016/j.surfcoat.2023.129698 ↗