Early stages of dissolution corrosion in 316L and DIN 1.4970 austenitic stainless steels with and without anticorrosion coatings in static liquid lead-bismuth eutectic (LBE) at 500 °C

Charalampopoulou, Evangelia; Lambrinou, Konstantina; Donck, Tom Van der; Paladino, Boris; Fonzo, Fabio Di; Azina, Clio; Eklund, Per; Mráz, Stanislav; Schneider, Jochen M.; Schryvers, D.; Delville, Rémi

doi:10.1016/j.matchar.2021.111234

Cited by 40 publications

(4 citation statements)

References 54 publications

(151 reference statements)

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Higher swelling resistance is pursued via microstructure stabilisation with selected alloying elements (for instance AIM1 and its bettered version AIM2) [269][270][271]. Enhanced corrosion resistance is sought for with corrosion barriers, either by implanting aluminum to change the surface composition and induce the formation of a protective alumina layer [272,273], or by directly depositing alumina (or other ceramics) layers to coat the metallic substrate [274][275][276]. Alternatively, aluminum is added to the alloy composition, to enable the formation of a protective alumina layer that self-heals through contact with the oxygen that is contained in the circulating fluids, so-called alumina forming austenitic (AFA) steels [277][278][279][280][281].…”

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

View full text Add to dashboard Cite

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.

show abstract

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

View full text Add to dashboard Cite

show abstract

“…The process is dominated by oxidation corrosion under high oxygen content. [27][28][29] The surface of 316SS alloy was rapidly oxidized, and multioxide layers containing an outer layer of Fe 3 O 4 and an inner layer of Fe-Cr oxide were formed under the oxygen content of 10 −2 wt%. This is also the fundamental reason for the quality increase.…”

Section: Discussionmentioning

confidence: 99%

Corrosion behavior of 316 stainless steel arc parts in liquid lead at 650 °C under high oxygen concentrations

et al. 2022

View full text Add to dashboard Cite

show abstract

“…1,2 Their structure and chemical composition provide them with a unique combination of metallic and ceramic properties. 3 MAX phases have been shown to be promising for a variety of applications, partic-ularly extreme environments, [4][5][6][7][8][9] but they are also used as precursors for the synthesis of their well-known 2D derivatives, the so-called MXenes. 10,11 The chemical versatility of MAX phases has been evidenced in the last years, by the discovery of no less than 180 different MAX phases.…”

Section: Introductionmentioning

confidence: 99%

Yttrium incorporation in Cr₂AlC: On the metastable phase formation and decomposition of (Cr,Y)₂AlC MAX phase thin films

et al. 2022

Self Cite

View full text Add to dashboard Cite

Herein we report on the synthesis of a metastable (Cr,Y)2AlC MAX phase solid solution by co‐sputtering from a composite Cr–Al–C and elemental Y target, at room temperature, followed by annealing. However, direct high‐temperature synthesis resulted in multiphase films, as evidenced by X‐ray diffraction analyses, room‐temperature depositions, followed by annealing to 760°C led to the formation of phase pure (Cr,Y)2AlC by diffusion. Higher annealing temperatures caused a decomposition of the metastable phase into Cr2AlC, Y5Al3, and Cr‐carbides. In contrast to pure Cr2AlC, the Y‐containing phase crystallizes directly in the MAX phase structure instead of first forming a disordered solid solution. Furthermore, the crystallization temperature was shown to be Y‐content dependent and was increased by ∼200°C for 5 at.% Y compared to Cr2AlC. Calculations predicting the metastable phase formation of (Cr,Y)2AlC and its decomposition are in excellent agreement with the experimental findings.

show abstract

Early stages of dissolution corrosion in 316L and DIN 1.4970 austenitic stainless steels with and without anticorrosion coatings in static liquid lead-bismuth eutectic (LBE) at 500 °C

Cited by 40 publications

References 54 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

Corrosion behavior of 316 stainless steel arc parts in liquid lead at 650 °C under high oxygen concentrations

Yttrium incorporation in Cr₂AlC: On the metastable phase formation and decomposition of (Cr,Y)₂AlC MAX phase thin films

Contact Info

Product

Resources

About

Early stages of dissolution corrosion in 316L and DIN 1.4970 austenitic stainless steels with and without anticorrosion coatings in static liquid lead-bismuth eutectic (LBE) at 500 °C

Cited by 40 publications

References 54 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

Corrosion behavior of 316 stainless steel arc parts in liquid lead at 650 °C under high oxygen concentrations

Yttrium incorporation in Cr2AlC: On the metastable phase formation and decomposition of (Cr,Y)2AlC MAX phase thin films

Contact Info

Product

Resources

About

Early stages of dissolution corrosion in 316L and DIN 1.4970 austenitic stainless steels with and without anticorrosion coatings in static liquid lead-bismuth eutectic (LBE) at 500 °C

Yttrium incorporation in Cr₂AlC: On the metastable phase formation and decomposition of (Cr,Y)₂AlC MAX phase thin films