DOE OSTI · 2574193
Environmental degradation testing of Alloy 709
Abstract
Alloy 709 is an advanced austenitic stainless steel developed to meet the demanding conditions of sodium fast reactors (SFRs) but may also be of use for lead fast reactors, high temperature gas reactors, and molten salt reactors. Understanding environmental degradation modes and quantifying degradation rates are crucial to ensure the long-term, reliable operation of these reactors. This paper discusses recent neutron irradiation results, future neutron irradiation test plans, and sodium corrosion testing to communicate current best understanding of the performance of Alloy 709 in SFR environments.
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Jokisaari, Andrea M [Idaho National Laboratory] (ORCID:0000000249455714), Massey, Caleb [Oak Ridge National Laboratory], Chen, Yiren [Argonne National Laboratory], Johnson, Drew Coulson [Idaho National Laboratory]. 2025-05-15. Environmental degradation testing of Alloy 709. https://www.osti.gov/biblio/2574193
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