{"title":"SA508 Gr. 1a LAS和SA312 TP316 SS在位移控制模式下的极低周疲劳行为","authors":"Sang Eon Kim , Jin Weon Kim , Jong-Sung Kim","doi":"10.1016/j.net.2025.103938","DOIUrl":null,"url":null,"abstract":"<div><div>This study investigates the deformation and failure behavior of two nuclear structural materials—SA508 Gr.1a low-alloy steel (LAS) and SA312 TP316 stainless steel (SS)—in the very low cycle fatigue (VLCF) regime. Displacement-controlled cyclic tests were performed on notched round-bar specimens with two notch radii (R1.5 and R6.0), spanning both low cycle fatigue (LCF) and VLCF regimes. All tests were conducted at room temperature (RT) under quasi-static loading.</div><div>In the VLCF regime, SA312 TP316 SS exhibited pronounced cyclic hardening that intensified with smaller notch radius and larger displacement amplitude, whereas SA508 Gr.1a LAS showed negligible hardening with little sensitivity to notch radius. Even in the VLCF regime, no significant reduction in fatigue life was observed when the fatigue life exceeded 10 cycles for either material; the fatigue life could be appropriately described by the Coffin–Manson relationship established from the LCF regime. Regardless of the material type or notch radius, all specimens in the VLCF regime with more than 10 cycles failed due to surface cracking, which is a typical failure mode in the LCF regime.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 2","pages":"Article 103938"},"PeriodicalIF":2.6000,"publicationDate":"2025-09-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Very low cycle fatigue behavior of SA508 Gr. 1a LAS and SA312 TP316 SS in displacement-control mode cyclic loads\",\"authors\":\"Sang Eon Kim , Jin Weon Kim , Jong-Sung Kim\",\"doi\":\"10.1016/j.net.2025.103938\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>This study investigates the deformation and failure behavior of two nuclear structural materials—SA508 Gr.1a low-alloy steel (LAS) and SA312 TP316 stainless steel (SS)—in the very low cycle fatigue (VLCF) regime. Displacement-controlled cyclic tests were performed on notched round-bar specimens with two notch radii (R1.5 and R6.0), spanning both low cycle fatigue (LCF) and VLCF regimes. All tests were conducted at room temperature (RT) under quasi-static loading.</div><div>In the VLCF regime, SA312 TP316 SS exhibited pronounced cyclic hardening that intensified with smaller notch radius and larger displacement amplitude, whereas SA508 Gr.1a LAS showed negligible hardening with little sensitivity to notch radius. Even in the VLCF regime, no significant reduction in fatigue life was observed when the fatigue life exceeded 10 cycles for either material; the fatigue life could be appropriately described by the Coffin–Manson relationship established from the LCF regime. Regardless of the material type or notch radius, all specimens in the VLCF regime with more than 10 cycles failed due to surface cracking, which is a typical failure mode in the LCF regime.</div></div>\",\"PeriodicalId\":19272,\"journal\":{\"name\":\"Nuclear Engineering and Technology\",\"volume\":\"58 2\",\"pages\":\"Article 103938\"},\"PeriodicalIF\":2.6000,\"publicationDate\":\"2025-09-25\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Technology\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S1738573325005066\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Technology","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S1738573325005066","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Very low cycle fatigue behavior of SA508 Gr. 1a LAS and SA312 TP316 SS in displacement-control mode cyclic loads
This study investigates the deformation and failure behavior of two nuclear structural materials—SA508 Gr.1a low-alloy steel (LAS) and SA312 TP316 stainless steel (SS)—in the very low cycle fatigue (VLCF) regime. Displacement-controlled cyclic tests were performed on notched round-bar specimens with two notch radii (R1.5 and R6.0), spanning both low cycle fatigue (LCF) and VLCF regimes. All tests were conducted at room temperature (RT) under quasi-static loading.
In the VLCF regime, SA312 TP316 SS exhibited pronounced cyclic hardening that intensified with smaller notch radius and larger displacement amplitude, whereas SA508 Gr.1a LAS showed negligible hardening with little sensitivity to notch radius. Even in the VLCF regime, no significant reduction in fatigue life was observed when the fatigue life exceeded 10 cycles for either material; the fatigue life could be appropriately described by the Coffin–Manson relationship established from the LCF regime. Regardless of the material type or notch radius, all specimens in the VLCF regime with more than 10 cycles failed due to surface cracking, which is a typical failure mode in the LCF regime.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development