Evaluation of cobalt free coatings as hardfacing material candidates in sodium-cooled fast reactor and effect of oxygen in sodium on the tribological behaviour
| Autor: | Gilles Rolland, Cécile Blanc, Brigitte Duprey, Hicham Maskrot, Michel Tabarant, J. L. Courouau, Fabien Rouillard, Thorsten Marlaud, Martine Blat-Yrieix, Pascal Aubry, Laetitia Nicolas, Raphaël Robin |
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| Přispěvatelé: | Service de la Corrosion et du Comportement des Matériaux dans leur Environnement (SCCME), Département de Physico-Chimie (DPC), CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay, Service d'études analytiques et de réactivité des surfaces (SEARS), Service des Recherches Métallurgiques Appliquées (SRMA), Département des Matériaux pour le Nucléaire (DMN), EDF (EDF), FRAMATOME |
| Jazyk: | angličtina |
| Rok vydání: | 2019 |
| Předmět: |
Materials science
020502 materials Metallurgy Hardfacing 02 engineering and technology engineering.material lcsh:TK9001-9401 Corrosion Surface coating 020303 mechanical engineering & transports Sodium-cooled fast reactor 0205 materials engineering 0203 mechanical engineering Stellite Breeder reactor engineering lcsh:Nuclear engineering. Atomic power [CHIM]Chemical Sciences Galling Austenitic stainless steel |
| Zdroj: | EPJ N-Nuclear Sciences & Technologies EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2019, 5, pp.10. ⟨10.1051/epjn/2019025⟩ EPJ Nuclear Sciences & Technologies, Vol 5, p 10 (2019) EPJ N-Nuclear Sciences & Technologies, 2019, 5, pp.10. ⟨10.1051/epjn/2019025⟩ |
| ISSN: | 2491-9292 |
| DOI: | 10.1051/epjn/2019025⟩ |
| Popis: | The feedback produced by operating Sodium-cooled Fast Reactors (SFRs) has shown the importance of material tribological properties. Where galling or adhesive wear cannot be allowed, hardfacing alloys, known to be galling-resistant coatings, are usually applied on rubbing surfaces. The most used coating is the cobalt-base alloy named Stellite 6® because of its outstanding friction and wear behaviour. Nevertheless, cobalt is an element which activates in the reactor leading to complex management of safety during reactor maintenance and mainly decommissioning. As a consequence, a collaborative work between CEA, EDF and FRAMATOME has been launched for selecting promising cobalt-free hardfacing alloys for the 600 MWe Sodium-cooled Fast breeder reactor project named ASTRID. Several nickel-base alloys have been selected from literature review then deposited by Plasma Transferred Arc or Laser Cladding on 17Cr austenitic stainless steel 316L(N) according to RCC-MRx Code (AFCEN Code). Among the numerous properties required for qualifying their use as hardfacing alloys in SFR, good corrosion behaviour and good friction and wear behaviour in sodium are essential. First results on these properties are shown in this article. Firstly, the corrosion behaviour of all coatings was evaluated through exposure tests in purified sodium for 5000 h at 400 °C. All coatings showed an acceptable corrosion behaviour in sodium. Finally, the friction and wear properties of one alloy candidate, NiCrBSi alloy, were studied in sodium in a dedicated designed facility. The influence of the oxygen concentration in sodium on the friction and wear properties was evaluated. |
| Databáze: | OpenAIRE |
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