Nickel-chromium (Ni–Cr) coatings deposited by magnetron sputtering for accident tolerant nuclear fuel claddings

Sidelev, Dmitrii V.; Kashkarov, Egor; Сыртанов, М. С.; Кривобоков, В. П.

doi:10.1016/j.surfcoat.2019.04.057

Cited by 60 publications

(29 citation statements)

References 52 publications

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“…The coatings were deposited on E110 alloy samples using the ion-plasma installation equipped with the multi-cathode magnetron sputtering systems and planetary substrateholder. More details about the deposition system are presented in [23].…”

Section: Coating Depositionmentioning

confidence: 99%

Protection of Zr Alloy under High-Temperature Air Oxidation: A Multilayer Coating Approach

et al. 2021

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Metallic Cr and multilayer CrN/Cr coatings with a thickness of 2.5 µm were deposited onto E110 alloy by magnetron sputtering. Oxidation tests in air were performed at 1100 °C for 10–40 min. The gravimetric measurements showed better protective properties of multilayer CrN/Cr coatings in comparison with metallic Cr coating. Multilayer coating prevented fast Cr–Zr inter-diffusion by the formation of a ZrN layer beneath the coating. The appearance of ZrN is caused by interaction with nitrogen formed from the decomposition of CrN to Cr2N phases. Optical microscopy revealed a residual Cr layer for the multilayer CrN (0.25 µm)/Cr (0.25 µm) coating for all the oxidation periods. Additional in situ X-ray diffraction (XRD) studies of coated alloy during linear heating up to 1400 °C showed that the formation of the Cr2Zr phase in the case of multilayer coatings occurred at a higher (~150 °C) temperature compared to metallic Cr. Multilayer coatings can decrease the nitrogen effect for Zr alloy oxidation. Uniform and thinner oxide layers of Zr alloy were observed when the multilayer coatings were applied. The highest oxidation resistance belonged to the CrN/Cr coating with a multilayer step of 0.25 µm.

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Section: Coating Depositionmentioning

confidence: 99%

Protection of Zr Alloy under High-Temperature Air Oxidation: A Multilayer Coating Approach

et al. 2021

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“…37 through 45, although there have been more recent material corrosion/erosion studies for the application of molten hydroxides for thermal energy storage systems 30,[46][47][48][49] and electric storage battery applications. 50 It is also possible that recent efforts in additive manufacturing and spray techniques in the development of coatings for advanced technology fuels/accident tolerant fuels 51 (ATFs) may be leveraged to develop coatings that are far more resistant to corrosion/erosion by hydroxides. However, further investigation of such corrosion-resistant materials, coatings, and manufacturing methods is beyond the scope of the current study.…”

Section: Iib Candidate Structural Materialsmentioning

confidence: 99%

“…Such lattice fuel concepts could be used in compact, thermalspectrum, high-temperature (700°C) small modular reactors (SMRs). For an SMR with a bare core size of diameter = height = 163.3 cm, there are several lattice design concepts identified that could achieve modest power densities (up to 18 MW/m 3 ) that are higher than those found typically in high-temperature gas cooled reactors (~ 2 to 10 MW/m 3 ) [IAEA Technical Document 1382(2019; Report PNR-131-20110914, Delft University, Netherlands (2011)], although lower than those found typically in SMRs based on light water reactor technology (for example, the NuScale SMR has a volumetric power density of ~47 MW/m 3 ) [Proc. PBNC 2018, p. 270 (2018].…”

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confidence: 99%

Initial Exploratory Reactor Physics Assessment of Nonconventional Fuel Concepts for Very Compact Small Modular Reactors Using Hydroxides as Coolants and/or Moderators

Bromley

2021

Nuclear Technology

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In this study, lattice physics calculations were carried out to evaluate the reactor physics characteristics of different advanced fuel lattices cooled with 7 LiOH/NaOH or FLiBe and moderated externally by graphite and various types of metal hydroxides, such as 7 LiOH, 7 LiOD, Mg(OD) 2 , and ZrE(OD) 4 . The lithium in these compounds is enriched to 99.995 at. % 7 Li/Li. Such lattice fuel concepts could be used in compact, thermalspectrum, high-temperature (700°C) small modular reactors (SMRs). For an SMR with a bare core size of diameter = height = 163.3 cm, there are several lattice design concepts identified that could achieve modest power densities (up to 18 MW/m 3 ) that are higher than those found typically in high-temperature gas cooled reactors (~ 2 to 10 MW/m 3 ) [IAEA Technical Document 1382(2019; Report PNR-131-20110914, Delft University, Netherlands (2011)], although lower than those found typically in SMRs based on light water reactor technology (for example, the NuScale SMR has a volumetric power density of ~47 MW/m 3 ) [Proc. PBNC 2018, p. 270 (2018]. In addition, there are lattice designs identified for the fixed core size that could achieve high fuel burnup (up to 126 MWd/kg), long core lifetimes (up to 24 years before refueling), very good fissile utilization (up to 640 MWd/kg-fissile), and very good relative uranium utilization (up to 44% of that achieved with a conventional pressure-tube heavy water reactor using natural uranium fuel). The best lattice concept found to maximize fuel burnup with 7 LiOH/NaOH coolant was an 18-cm-pitch lattice with ZrE(OD) 4 external moderator (126.5 MWd/kg). The best lattice concept for FLiBe coolant was a 16-cm-pitch lattice with 7 LiOH external moderator (125.99 MWd/kg). Although it is recognized that there are numerous and challenging technical issues to be resolved, particularly with corrosion and materials science, the potential use of hydroxides as coolants and/or external moderators could lead to very important performance improvements for very small and compact SMRs.

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“…Chromium coatings were deposited onto the welded samples by using the vacuum installation equipped with multi-cathode magnetron sputtering systems. The detailed description of the installation is presented in previous study [27]. Firstly, the samples were rinsed with acetone in an ultrasonic bath and dried by compressed air for 2 min.…”

Section: Sample Preparationmentioning

confidence: 99%

High-Temperature Oxidation of Cr-Coated Resistance Upset Welds Made from E110 Alloy

2021

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The resistance upset welds (RUW) made from E110 alloy without and with Cr coatings were oxidized in air atmosphere at 1100 °C for 2, 10 and 30 min. The cross-section microstructure, elemental composition and hardness were studied before and after oxidation using optical and scanning electron microscopy, and indentations in welding region. The RUW welding does not noticeably change oxidation kinetics of E110 alloy. The most crucial effect has surface non-regularities formed after welding, which prevent uniform coating deposition on full surface of welded cladding tube and end plug. Cr coating deposition can strongly reduce oxidation of welded E110 alloy, while additional post-processing treatment should be applied to improve surface morphology after RUW welding. Several suggestions favorable to development of ATF Zr-based claddings using Cr coating deposition on welded nuclear rods were discussed.

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Nickel-chromium (Ni–Cr) coatings deposited by magnetron sputtering for accident tolerant nuclear fuel claddings

Cited by 60 publications

References 52 publications

Protection of Zr Alloy under High-Temperature Air Oxidation: A Multilayer Coating Approach

Protection of Zr Alloy under High-Temperature Air Oxidation: A Multilayer Coating Approach

Initial Exploratory Reactor Physics Assessment of Nonconventional Fuel Concepts for Very Compact Small Modular Reactors Using Hydroxides as Coolants and/or Moderators

High-Temperature Oxidation of Cr-Coated Resistance Upset Welds Made from E110 Alloy

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