Hydrogenation Behavior of Cr-Coated Resistance Upset Welds of E110 Zirconium Alloy
Source abstract
Abstract
The hydrogenation behavior of Cr-coated resistance upset welds (RUW) of E110 zirconium alloy was investigated at 360, 450 and 900 °C and a hydrogen pressure of 2 bar. The deposition of Cr coating, via magnetron sputtering, can decrease the hydrogen absorption rate of an RUW Zr alloy. The activation energy for the hydrogen absorption of Cr-coated specimens (84 kJ/mol) is higher in comparison with uncoated ones (71 kJ/mol), which indicates the deceleration of the hydriding of welded Zr alloys in the case of Cr coating deposition. A Cr coating can limit the formation of radially oriented hydrides and the hardening of RUW specimens at 360 and 450 °C. No significant difference in the hydrogen absorption rate was found at 900 °C. The application of Cr coating deposition to protect resistance-upset-welded Zr alloys in a hydrogen atmosphere is discussed.
Source: crossref · Quality: baseline
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.
Affiliations
School of Nuclear Science and Engineering, National Research Tomsk Polytechnic University, 634050 Tomsk, Russia
Funding
Russian Science Foundation
References (39)
Show source-provided references
1. Creep behavior of niobium-modified zirconium alloys10.1016/j.jnucmat.2007.08.019 ↗
2. Corrosion of zirconium alloys10.1016/B978-0-08-056033-5.00063-X ↗
3. Accident tolerant fuels for LWRs: A perspective10.1016/j.jnucmat.2013.12.005 ↗
4. The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts10.1016/j.jnucmat.2022.154152 ↗
5. Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings
6. Construction of chromium coatings with (200) preferred orientation and exploration the high-temperature steam oxidation properties10.1016/j.jnucmat.2022.153660 ↗
7. Silicon carbide composite for light water reactor fuel assembly applications10.1016/j.jnucmat.2013.12.004 ↗
8. DLI-MOCVD CrxCy coating to prevent Zr-based cladding from inner oxidation and secondary hydriding upon LOCA conditions10.1016/j.jnucmat.2021.152953 ↗
9. Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding10.1016/j.jnucmat.2017.12.035 ↗
10. Effect of N content on microstructure and properties of (AlTiCrNiTa)N coatings for accident-tolerant fuels10.1016/j.intermet.2022.107728 ↗
11. Influence of Al content on the oxidation behavior of CrAl coating on Zry-4 alloys in 1200 °C steam10.1016/j.corsci.2022.110115 ↗
12. Enhancement of oxidation resistance of Cr/CrN composite coating on Zr-4 surface by high lattice-matched interfacial Engineering10.1016/j.jnucmat.2022.154162 ↗
13. Steam oxidation behavior of ZrO2/Cr-coated pure zirconium prepared by plasma electrolytic oxidation followed by filtered cathodic vacuum arc deposition10.1016/j.jallcom.2021.160798 ↗
14. High-temperature oxidation of Zr-1Nb zirconium alloy with protective Cr/Mo coating10.1016/j.surfcoat.2022.128459 ↗
15. Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors10.1016/j.jnucmat.2019.02.018 ↗
16. 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 ↗
17. Hydride formation in zirconium alloys10.1007/s11837-012-0479-x ↗
18. Embrittlement of pre-hydrided Zircaloy-4 by steam oxidation under simulated LOCA transients10.1016/j.jnucmat.2015.11.008 ↗
19. Microstructure and mechanical properties of Zircaloy-4 cladding hydrogenated at temperatures typical for loss-of-coolant accident (LOCA) conditions10.1016/j.nucengdes.2014.06.022 ↗
20. Phase transformations during cooling from the βZr phase temperature domain in several hydrogen-enriched zirconium alloys studied by in situ and ex situ neutron diffraction10.1016/j.actamat.2020.08.061 ↗
21. Investigation of the impact of coatings on corrosion and hydrogen uptake of Zircaloy-410.1016/j.jnucmat.2015.09.041 ↗
22. Hydrogen absorption by Ti-implanted Zr-1Nb alloy10.1016/j.ijhydene.2017.12.003 ↗
23. SiC coating as hydrogen permeation reduction and oxidation resistance for nuclear fuel cladding10.1080/00223131.2015.1020901 ↗
24. H2 permeation behavior of Cr2AlC and Ti2AlC max phase coated Zircaloy-4 by neutron radiography10.14311/AP.2018.58.0069 ↗
25. Hydrogenation behavior of Cr-coated laser beam welds of E110 zirconium alloy10.1016/j.jnucmat.2022.153980 ↗
26. Sidelev, D., Ruchkin, S., and Kashkarov, E. (2021). High-Temperature Oxidation of Cr-Coated Resistance Upset Welds Made from E110 Alloy. Coatings, 11.10.3390/coatings11050577 ↗
27. A comparative study on high-temperature air oxidation of Cr-coated E110 zirconium alloy deposited by magnetron sputtering and electroplating10.1016/j.surfcoat.2022.128134 ↗
28. Effect of titanium ion implantation and deposition on hydrogenation behavior of Zr-1Nb alloy10.1016/j.surfcoat.2016.07.111 ↗
29. The kinetics of hydrogen desorption from and adsorption on zirconium hydride10.1016/j.jnucmat.2009.12.008 ↗
30. Hydrogen absorption by zirconium alloys at high temperatures
31. Reorientation of Hydrides in Unirradiated Clad Tubes Made of Alloy E110 under Conditions Simulating Long-Term Dry Storage of Spent Nuclear Fuel10.1134/S0031918X21090076 ↗
32. Effects of hydride rim on the ductility of Zircaloy-4 cladding10.1016/j.jnucmat.2019.06.007 ↗
33. Kashkarov, E.B., Gusev, K.S., Ashikhmin, D.A., Abdulmenova, A.V., and Sidelev, D.V. (2022). Oxidation and Mechanical Behavior of Cr-Coated Laser Beam Welds Made from E110 Zirconium Alloy. Coatings, 12.10.3390/coatings12111623 ↗
34. Effect of Final Annealing Temperature on Corrosion Resistance of SZA-6 Zirconium Alloy Cladding Tubes10.4028/www.scientific.net/MSF.944.488 ↗
35. Properties of welded joints from alloy Zr-2.5%Nb after electron-beam local thermocycling10.1007/s11041-014-9688-y ↗
36. The dilatational misfit of zirconium hydrides precipitated in zirconium10.1016/0022-3115(73)90022-6 ↗
37. Microscopic stress and crystallographic orientation of hydrides precipitated in Zr-1Nb-0.01Cu cladding tube investigated by high-energy X-ray diffraction and EBSD10.1016/j.jnucmat.2020.152534 ↗
38. Hydrogen in zirconium part 1
39. AREVA NP’s enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding10.1016/j.net.2017.12.004 ↗