Al rich PVD protective coatings: A promising approach to prevent T91 steel corrosion in stagnant liquid lead

Miorin, Enrico; Montagner, Francesco; Zin, Valentina; Giuranno, Donatella; Ricci, E.; Pedroni, Matteo; Spampinato, Valentina; Vassallo, E.; Deambrosis, Silvia Maria

doi:10.1016/j.surfcoat.2019.124890

Cited by 51 publications

(12 citation statements)

References 62 publications

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“…resistance at high temperature [93,293,295]. Finally, the methods to improve F/M steel corrosion resistance are the same as in austenitic steels: either surface modifications/coatings [307][308][309][310] or alloy composition tuning with aluminum addition, so-called FeCrAl (currently intensively studied for ATF cladding) [311][312][313][314][315]. The latter may also be ODS, giving rise to a potentially very promising material (ODS-FeCrAl) that is simultaneously resistant to irradiation, creep and corrosion [316][317][318].…”

Section: Annex 3-pathways To Nuclear Materials Improvement For Next G...mentioning

confidence: 99%

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Malerba

Mazouzi²,

Bertolus

et al. 2022

Energies

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Nuclear energy is presently the single major low-carbon electricity source in Europe and is overall expected to maintain (perhaps eventually even increase) its current installed power from now to 2045. Long-term operation (LTO) is a reality in essentially all nuclear European countries, even when planning to phase out. New builds are planned. Moreover, several European countries, including non-nuclear or phasing out ones, have interests in next generation nuclear systems. In this framework, materials and material science play a crucial role towards safer, more efficient, more economical and overall more sustainable nuclear energy. This paper proposes a research agenda that combines modern digital technologies with materials science practices to pursue a change of paradigm that promotes innovation, equally serving the different nuclear energy interests and positions throughout Europe. This paper chooses to overview structural and fuel materials used in current generation reactors, as well as their wider spectrum for next generation reactors, summarising the relevant issues. Next, it describes the materials science approaches that are common to any nuclear materials (including classes that are not addressed here, such as concrete, polymers and functional materials), identifying for each of them a research agenda goal. It is concluded that among these goals are the development of structured materials qualification test-beds and materials acceleration platforms (MAPs) for materials that operate under harsh conditions. Another goal is the development of multi-parameter-based approaches for materials health monitoring based on different non-destructive examination and testing (NDE&T) techniques. Hybrid models that suitably combine physics-based and data-driven approaches for materials behaviour prediction can valuably support these developments, together with the creation and population of a centralised, “smart” database for nuclear materials.

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Section: Annex 3-pathways To Nuclear Materials Improvement For Next G...mentioning

confidence: 99%

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Malerba

Mazouzi²,

Bertolus

et al. 2022

Energies

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“…The corrosion resistance of a T91 steel coated with alumina by magnetron sputtering PVD was also studied by E. Miorin in stagnant liquid Pb at 550 • C for 1200 h. The results showed the growth of a non-adherent and wrinkled oxide layer on the uncoated steel, which had a variable macroscopic morphology on different surface zones and appeared detached from the bulk in several places. In contrast, the alumina coating of the T91 steel appeared intact, compact, and adherent to the substrate, with a uniform thickness [51].…”

Section: Corrosion Testmentioning

confidence: 92%

Behaviour Aspects of an EB-PVD Alumina (Al2O3) Film with an Interlayer (NiCrAlY) Deposited on AISI 316L Steel Investigated in Liquid Lead

Petrescu

Nitu

Golgovici

et al. 2023

Metals

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The use of lead as a primary coolant is one of the most attractive options for next-generation lead-cooled fast reactor systems (LFR). Despite many favourable features, liquid Pb is a harsh environment that induces many problems on metallic components. Therefore, candidate materials for LFR must be qualified, and the solutions to improve their properties must be found. This paper’s objective is to present the results obtained from the tensile tests of AISI 316L steel in liquid lead at 400 °C, 450 °C, and 500 °C, and the short-term corrosion tests performed on coated and uncoated AISI 316L steel at 550 °C. The coating was made of Al2O3 with a CrNiAlY interlayer using the electron beam-physical vapor deposition (EB-PVD) technique. Both the mechanical and corrosion tests were performed in stagnant lead saturated with oxygen. After testing, the specimens were characterised by several analyses, including scanning electron microscopy (SEM), energy-dispersive X-ray spectroscopy (EDS), optical microscopy (OM), scratching test, and Vickers micro-hardness test. The tensile test results highlight the ductile behaviour of the material, and in the case of the corrosion tests, the coatings prove to be effective in protecting the substrate from the harsh environment.

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“…Ceramic candidate coating materials include oxides, carbides, nitrides, etc. [243,596,626,633,634,[640][641][642][643][644]. Oxides, such as ZrO The main problem of ceramic coatings is the lack of damage self-healing in service.…”

Section: Coating Deposition and Surface Modification Of Steelsmentioning

confidence: 99%

Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors

Gong

Short

Auger

et al. 2022

Progress in Materials Science

170

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Al rich PVD protective coatings: A promising approach to prevent T91 steel corrosion in stagnant liquid lead

Cited by 51 publications

References 62 publications

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Behaviour Aspects of an EB-PVD Alumina (Al2O3) Film with an Interlayer (NiCrAlY) Deposited on AISI 316L Steel Investigated in Liquid Lead

Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors

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