Published 2015 | Version v1
Book

Study of the oxidation mechanisms of 316LN steel in liquid sodium - 15407

  • 1. CEA, Centre de Saclay, DEN, DANS, DPC, SCCME, Laboratoire d'Etude de la Corrosion Non Aqueuse, F-91191 Gif-sur-Yvette (France)
  • 2. Ecole Centrale Paris, EA4038, Laboratoire de Genie des Procedes et Materiaux, F-92295 Chatenay-Malabry (France)
  • 3. CNRS, UMR8635, Groupe d'Etude de la Matiere Condensee, F-78035 Versailles (France)
  • 4. CEA, Centre de Saclay, DEN, DANS, DPC, SEARS, Laboratoire d'Ingenierie des Surfaces et Lasers, F-91191 Gif-sur-Yvette (France)
  • 5. CEA, Centre de Saclay, INSTN, UEPTN, Laboratoire Jannus, F-91191 Gif-sur-Yvette (France)

Description

The sodium cooled fast reactor is selected in France as the 4. generation of nuclear power plant. Reactors vessel, primary loop structures and heat exchangers will be made of austenitic stainless steels: 316LN is the reference material. To assess reactor service life time, corrosion of austenitic stainless steel by liquid sodium is studied in normal operating conditions as well as in transient conditions either expected or not. Oxygen is one of the impurities present in liquid sodium at the level of a few parts per million in weight. It presents a major effect on corrosion phenomena of austenitic stainless steel, although not totally understood yet, in increasing the iron solubility as well as its dissolution rate. Oxygen is also known to form sodium chromite scale (NaCrO2), those behavior is little documented in the literature. Based on corrosion tests performed in the static sodium test device ('CorroNa') at 550 and 650 Celsius degrees, sodium chromite scale (NaCrO2) is observed in slightly oxidizing conditions. Below the oxide scale, a chromium depleted layer is characterized. Some aspects of the morphology of this oxide scale and its properties are presented. To predict long term corrosion effects on materials (40-60 years), the oxidation mechanisms are investigated in order to identify the limiting step of the kinetics, as well as to understand the basic phenomenon at play in this complex corrosion phenomenon. This paper proposes that sodium oxide diffuses through the oxide scale and that the oxide scale grows inwards thanks to test achieved with inert corrosion marker and isotopic tracers (16O-18O). Tests are characterized by Rutherford Backscattered Spectroscopy (RBS), Nuclear Reaction Analysis (NRA), Glow Discharge Optical Emission Spectroscopy (GD-OES), and Secondary Ion Mass Spectroscopy (SIMS). In addition, these results are used to assess the sodium diffusion coefficient in the austenitic stainless steel. Moreover, in knowing chromium diffusion coefficient in stainless steel, kinetics assessment of oxidation is then made possible. (authors)

Availability note (English)

Available (USB stick) from: SFEN, 103 rue Reaumur, 75002 Paris (France)
Part of:
ICAPP 2015 Proceedings

Additional details

Publishing Information

Publisher
Societe Francaise d'Energie Nucleaire - SFEN
Imprint Place
Paris (France)
Imprint Title
ICAPP 2015 Proceedings
Imprint Pagination
3390 p.
Journal Page Range
p. 2869-2873

Conference

Title
Nuclear Innovations for a low-carbon future
Acronym
ICAPP 2015
Dates
3-6 May 2015
Place
Nice (France)

Optional Information

Notes
9 refs.