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Corrosion behaviour of a high strength nickel base alloy in Gas Cooled Reactors (GCR)

Abstract : Ni-Cr-W alloys are claimed to present high creep strength, a good hot workability together with improved oxidation resistance. Recently developed Haynes 230 could be a promising candidate material for the high temperature structures in Gas Cooled Reactors (GCR). However, corrosion resistance of Haynes 230 is unknown in the reactor specific environment namely impure He up to 850-950DC. Generally speaking the impurities in the cooling helium react with most Cr-containing alloys. They can produce surface scale formation, bulk carburisation and-or decarburization, depending on the gas chemistry, the alloy composition and the temperature. The changes in the bulk carbon content and the associated structural transformations can notably degrade the material mechanical properties and must definitely be precluded. Corrosion properties of Haynes 230 were investigated in a purposely-designed facility under different helium media at about 950DC. Short and longer experiments were carried out in simulated GCR coolant in order to assess the corrosion variability to test conditions. More specifically, the oxide scale formation and a deleterious reaction destructing the protective oxide layer were studied. Main factors impacting on this previous reaction, such as the carbon monoxide partial pressure in the gas atmosphere and the activity of the reactive elements in the alloy were investigated. The reaction mechanism is discussed in the light of published models.
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Submitted on : Thursday, November 7, 2019 - 3:54:25 PM
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  • HAL Id : cea-02354149, version 1




F. Rouillard, C Cabet, K. Wolski, A. Terlain, M. Tabarant. Corrosion behaviour of a high strength nickel base alloy in Gas Cooled Reactors (GCR). Journal of Nuclear Materials, Elsevier, 2007. ⟨cea-02354149⟩



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