Ian de CURIERES
- Autorité de Sûreté Nucléaire et de Radioprotection (ASNR)
Publications
Publications
Effect of dissolved oxygen and temperature on oxidation and stress corrosion cracking of 316L stainless steel in pressurized water reactors primary environment22nd International Conference on Environmental Degradation of materials in nuclear power systems, Association for Materials Protection and Performance (AMPP), Aug 2025, Long Beach, United States. Paper no. ED2025- 00020 |
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Effect of Dissolved Oxygen and Temperature on Oxidation and Stress Corrosion Cracking of 316L Stainless Steel in Nuclear Primary Environment22nd International conference on the Environmental Degradation of Materials in Nuclear Power Systems, Aug 2025, Long Beach (CA), United States |
Effet de l’oxygène dissous et de la température sur l’oxydation et la corrosion sous contrainte de l’acier inoxydable 316L en milieu primaire de réacteur à eau pressuriséeJournées jeunes chercheurs 2025 de la commission CSC et FPH du CEFRACOR, CEFRACOR – Commission Corrosion Sous Contrainte – Fatigue – Corrosion, Nov 2025, Grenoble, France. page 189 |
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Effect of Dissolved Oxygen and Mechanical Loading on the Surface and Intergranular Oxidation of a 316L Stainless Steel in Simulated Primary Water of Nuclear Reactors11th International Symposium on High Temperature Corrosion and Materials Protection (HTCPM 2024), CEFRACOR - Centre Français de l’Anticorrosion, Jun 2024, Ile des Embiez, France. pp.sans objet |
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Effect of Dissolved Oxygen on Stress Corrosion Cracking of 316L Stainless Steel in Nuclear Primary EnvironmentEUROCORR 2024 (European Corrosion Congress – congrès annuel de l’European Federation of Corrosion), EFC – European Federation of Corrosion (congrès EUROCORR), Sep 2024, Paris, France |
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Stress corrosion cracking initiation of alloy 82 in hydrogenated steam18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, TMS (The Minerals, Metals & Materials Society); EDM 2017, Aug 2017, Portland, United States. pp.175-189, ⟨10.1007/978-3-030-04639-2_11⟩ |
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Stress Corrosion Cracking of Nickel Base Alloys in PWR Primary WaterMINOS 2012 - Workshop on Materials Innovation for Nuclear Optimized Systems, Dec 2012, Saclay, France. pp.04003, ⟨10.1051/epjconf/20135104003⟩ |
The effect of sulfur and lead on the corrosion of steam generator tubes made of alloy 690 thermally treated exposed to a wet steam environment at 320 °CCorrosion Science, 2025, 256, pp.113202. ⟨10.1016/j.corsci.2025.113202⟩ |