Abstract
Due to its exceptional high-temperature properties, Alloy 709 (UNS 31025), an advanced austenitic stainless steel, has been selected by the U.S. Department of Energy, Office of Nuclear Energy, Advanced Reactor Technologies Program for qualification as a Class A construction material in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section III, Division 5 for high temperature reactor applications. This initiative encompasses a comprehensive staged qualification plan for code cases with progressively longer design lives of 100,000, 300,000, and 500,000 hr, as long-term test data become available. A significant portion of this effort focuses on creating a data package that is essential for establishing material-specific design parameters for Alloy 709, intended for use in sodium fast reactors, molten salt reactors, and gas-cooled reactors. Data generation for the initial 100,000-hr code case was completed at the end of 2024. A key component of this data package involves conducting fatigue and creep-fatigue testing at elevated temperatures to develop fatigue design curves and the damage envelope for the creep-fatigue interaction diagram (D-diagram), both of which are common to all three code cases. Strain-controlled fatigue and creep-fatigue tests have been conducted on three commercial heats of Alloy 709 plates at the Oak Ridge National Laboratory and the Idaho National Laboratory. The comprehensive code case testing matrix includes strain ranges from 0.25 to 3%, hold times of up to 10 hr, and testing temperatures of 21, 427, 649, 760, 816, and 954 °C (70, 800, 1200, 1400, 1500, and 1750 °F). This paper summarizes the results of cyclic testing and provides a comprehensive analysis of the test results. It outlines the methodology for developing temperature-dependent fatigue curves and presents draft fatigue design curves for inclusion in the code cases. Furthermore, creep-fatigue test data with various tension hold times are used to support the development of the creep-fatigue interaction diagram. Both sets of design parameters are crucial for the code case data package.
| Original language | English |
|---|---|
| Title of host publication | Codes and Standards |
| Publisher | American Society of Mechanical Engineers (ASME) |
| ISBN (Electronic) | 9780791889046 |
| DOIs | |
| State | Published - 2025 |
| Event | ASME 2025 Pressure Vessels and Piping Conference, PVP 2025 - Montreal, Canada Duration: Jul 20 2025 → Jul 25 2025 |
Publication series
| Name | American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP |
|---|---|
| Volume | 1 |
| ISSN (Print) | 0277-027X |
Conference
| Conference | ASME 2025 Pressure Vessels and Piping Conference, PVP 2025 |
|---|---|
| Country/Territory | Canada |
| City | Montreal |
| Period | 07/20/25 → 07/25/25 |
Funding
The research was sponsored by the U.S. Department of Energy, Office of Nuclear Energy, under contract No. DEAC05-00OR22725 with Oak Ridge National Laboratory (ORNL), managed and operated by UT-Battelle, LLC, and under contract No. DE-AC07-05ID14517 with Idaho National Laboratory (INL), managed and operated by Battelle Energy Alliance, LLC. Programmatic direction was provided by the Office of Nuclear Reactors of the Office of Nuclear Energy. The contribution of Brad Hall and Charles S. Hawkins of ORNL in running the experiments is greatly appreciated. The authors acknowledge the technical support and valuable discussions with Dr. Peijun Hou of Imtech Corporation, Knoxville, Tennessee, and Dr. Richard Wright of Structural Alloys. Inc.
Keywords
- Alloy 709
- Code Case
- Creep-fatigue
- Fatigue