FY25 Status Update on A709 Code Case Testing at ANL

Technical Report · Sun Jun 01 04:00:00 EDT 2025

DOI:https://doi.org/10.2172/2570982· OSTI ID:2570982

Zhang, Xuan ^[1]; Listwan, Edward J. ^[2]

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1. Argonne National Laboratory (ANL), Argonne, IL (United States). Argonne Tandem Linac Accelerator System (ATLAS)
2. Argonne National Laboratory (ANL), Argonne, IL (United States)

This report provides an update on the status of the creep rupture testing on the precipitation-treated (PT) Alloy 709 samples fabricated from the first, the second and the third commercial heats, in support of the first, 100,000-hour Alloy 709 Code Case development under the American Society of Mechanical Engineers (ASME) Section III, Division 5 for high-temperature reactor construction. In Fiscal Year (FY) 25, no new tests were initiated, while 5 previously loaded tests were completed. This report presents an overview of the creep-rupture data gathered at Argonne National Laboratory (ANL) since FY21 that totaled 52 completed tests. Metallographic images showing crack morphologies in some representative samples ruptured in FY25 are also included. Key conclusions include: 1) the creep behavior of the three heats of Alloy 709 can be well described by the Larson-Miller relationship; 2) higher temperatures and larger stresses lead to shorter creep life and higher minimum creep rate; 3) Alloy 709 is overall very ductile under creep; 4) the crack morphologies near fracture surfaces are dependent on material’s grain size and test conditions.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE), Reactor Fleet and Advanced Reactor Development. Office of Nuclear Reactor Deployment
• DOE Contract Number: AC02-06CH11357
• OSTI ID: 2570982
• Report Number(s): ANL-ART--304; 197447
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE