{"status":"ok","message-type":"work","message-version":"1.0.0","message":{"indexed":{"date-parts":[[2026,6,19]],"date-time":"2026-06-19T07:30:20Z","timestamp":1781854220700,"version":"3.54.5"},"reference-count":35,"publisher":"MDPI AG","issue":"11","license":[{"start":{"date-parts":[[2022,6,3]],"date-time":"2022-06-03T00:00:00Z","timestamp":1654214400000},"content-version":"vor","delay-in-days":0,"URL":"https:\/\/creativecommons.org\/licenses\/by\/4.0\/"}],"funder":[{"name":"Department of Energy\u2019s Nuclear Energy University Programs","award":["#15-8582"],"award-info":[{"award-number":["#15-8582"]}]},{"name":"Department of Energy\u2019s Nuclear Energy University Programs","award":["#19-16987"],"award-info":[{"award-number":["#19-16987"]}]},{"name":"King Abdulaziz City for Science and Technology","award":["#15-8582"],"award-info":[{"award-number":["#15-8582"]}]},{"name":"King Abdulaziz City for Science and Technology","award":["#19-16987"],"award-info":[{"award-number":["#19-16987"]}]}],"content-domain":{"domain":[],"crossmark-restriction":false},"short-container-title":["Materials"],"abstract":"<jats:p>Creep\u2013fatigue interaction occurs in many structural components of high-temperature systems operating under cyclic and steady-state service conditions, such as in nuclear power plants, aerospace, naval, and other industrial applications. Thus, understanding micromechanisms governing high-temperature creep\u2013fatigue behavior is essential for safety and design considerations. In this work, stress-controlled creep\u2013fatigue tests of advanced austenitic stainless steel (Alloy 709) were performed at a 400 MPa stress range and 750 \u00b0C with tensile hold times of 0, 60, 600, 1800, and 3600 s, followed by microstructural examinations. The creep\u2013fatigue lifetime of the Alloy 709 was found to decrease with increasing hold time until reaching a saturation level where the number of cycles to failure did not exhibit a significant decrease. Softening behavior was observed at the beginning of the test, possibly due to the recovery of entangled dislocations and de-twining. In addition, hysteresis loops showed ratcheting behavior, although the mean stress was zero during creep\u2013fatigue cycling, which was attributed to activity of partial dislocations. Microstructural examination of the fracture surfaces showed that fatigue failure dominated at small hold times where the cracks initiated at the surface of the sample. Larger creep cracks were found for longer hold times with a lower probability of dimpled cavities, indicating the dominance of creep deformation. The results were compared with other commonly used stainless steels, and plausible reasons for the observed responses were described.<\/jats:p>","DOI":"10.3390\/ma15113984","type":"journal-article","created":{"date-parts":[[2022,6,3]],"date-time":"2022-06-03T08:01:18Z","timestamp":1654243278000},"page":"3984","update-policy":"https:\/\/doi.org\/10.3390\/mdpi_crossmark_policy","source":"Crossref","is-referenced-by-count":6,"title":["Stress-Controlled Creep\u2013Fatigue of an Advanced Austenitic Stainless Steel at Elevated Temperatures"],"prefix":"10.3390","volume":"15","author":[{"given":"Zeinab Y.","family":"Alsmadi","sequence":"first","affiliation":[{"name":"Department of Nuclear Engineering, North Carolina State University, Raleigh, NC 27695-7909, USA"}],"role":[{"vocabulary":"crossref","role":"author"}]},{"given":"Hamdy","family":"Abouelella","sequence":"additional","affiliation":[{"name":"Department of Nuclear Engineering, North Carolina State University, Raleigh, NC 27695-7909, USA"}],"role":[{"vocabulary":"crossref","role":"author"}]},{"ORCID":"https:\/\/orcid.org\/0000-0002-2068-4759","authenticated-orcid":false,"given":"Abdullah S.","family":"Alomari","sequence":"additional","affiliation":[{"name":"Department of Nuclear Engineering, North Carolina State University, Raleigh, NC 27695-7909, USA"},{"name":"Nuclear Science Research Institute, King Abdulaziz City for Science and Technology (KACST), P.O. Box 6086, Riyadh 11442, Saudi Arabia"}],"role":[{"vocabulary":"crossref","role":"author"}]},{"given":"K. L.","family":"Murty","sequence":"additional","affiliation":[{"name":"Department of Nuclear Engineering, North Carolina State University, Raleigh, NC 27695-7909, USA"}],"role":[{"vocabulary":"crossref","role":"author"}]}],"member":"1968","published-online":{"date-parts":[[2022,6,3]]},"reference":[{"key":"ref_1","unstructured":"Murty, K.L., Murty, K.L., and Charit, I. (2013). An Introduction to Nuclear Materials: Fundamentals and Applications, Wiley-VCH."},{"key":"ref_2","doi-asserted-by":"crossref","unstructured":"Odette, G.R., and Zinkle, S.J. (2019). Chapter 1-Overview of Structural Materials in Water-Cooled Fission Reactors. 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