Low cycle fatigue behavior of 316LN stainless steel hollow specimen in air and liquid lead–bismuth eutectic
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OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
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References (27)
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1. The MEGAPIE 1 MW target in support to ADS development: status of R&D and design10.1016/j.jnucmat.2004.07.007 ↗
2. Structural materials for Gen-IV nuclear reactors: challenges and opportunities10.1016/j.jnucmat.2008.08.044 ↗
3. Introduction to Generation IVnuclear reactors
4. Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors10.1016/j.pmatsci.2022.100920 ↗
5. Concetta F. Handbook on lead-bismuth eutectic alloy and lead properties, materials compatibility, thermal-hydraulics and technologies: 2015 Edition – introduction; 2015.
6. Structural materials for liquid metal cooled fast reactor fuel assemblies – operational behavior. Kerntechnik; 2012.
7. An overview of corrosion issues for the design and operation of high-temperature lead- and lead-bismuth-cooled reactor systems10.13182/NT04-A3540 ↗
8. Material performance in lead and lead-bismuth alloy
9. Liquid metal corrosion in nuclear reactor and accelerator driven systems10.1533/9780857095343.3.301 ↗
10. Material performance in lead and lead-bismuth alloy10.1016/B978-0-12-803581-8.00749-9 ↗
11. Low cycle fatigue behaviour of 15–15Ti at 20 and 550°C under vacuum10.1080/02670836.2019.1612593 ↗
12. Influence of PbBi environment on the low-cycle fatigue behavior of SNS target container materials10.1016/S0022-3115(03)00015-1 ↗
13. Fatigue behaviour of a martensitic and an austenitic steel in heavy liquid metals10.1016/j.proeng.2013.03.336 ↗
14. Influence of liquid lead and lead–bismuth eutectic on tensile, fatigue and creep properties of ferritic/martensitic and austenitic steels for transmutation systems10.1016/j.jnucmat.2011.04.047 ↗
15. Yas’kiv OI, Fedirko VM, Kukhar IS. Effect of lead and lead–bismuth eutectic melts on the fatigue life of steels of the martensitic and austenitic classes. Mater Sci 2014; 50: 102–8.10.1007/s11003-014-9697-4 ↗
16. Effect of temperature on low cycle fatigue behavior of T91 steel in liquid lead-bismuth eutectic environment at 150–550 °C10.1016/j.ijfatigue.2022.107344 ↗
17. X W. Research advance on liquid lead-bismuth eutectic corrosion resistant ferritic/martensitic and austenitic stainless steels. Acta Metall Sin 2023; 0-0.
18. LIMETS 3, a novel system for high strain fatigue testing in lead–bismuth eutectic10.1016/j.jnucmat.2013.10.064 ↗
19. Influence of LBE long term exposure and simultaneous fast neutron irradiation on the mechanical properties of T91 and 316L10.1016/j.jnucmat.2016.02.008 ↗
20. Effects of temperature and strain rate on the mechanical properties of T91 material tested in liquid lead bismuth eutectic10.1016/j.jnucmat.2006.05.034 ↗
21. Coen G, Van dB, J, Almazouzi A, Degrieck J. Investigation of the effect of lead-bismuth eutectic on the fracture properties of T91 and 316L. J Nucl Mater 2010; 398: 122–8.10.1016/j.jnucmat.2009.10.021 ↗
22. Chapter 6 - lead-cooled fast reactors (LFRs)
23. Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants10.1016/j.jnucmat.2020.152407 ↗
24. Corrosion behaviour of steels and refractory metals and tensile features of steels exposed to flowing PbBi in the LECOR loop10.1016/S0022-3115(03)00009-6 ↗
25. Corrosion behavior of T91 steel in liquid lead-bismuth eutectic at 550 °C: Effects of exposure time and dissolved oxygen concentration10.1016/j.corsci.2022.110405 ↗
26. Effect of LWR coolant environments on the fatigue life of reactor materials
27. Effects of strain rate on low-cycle fatigue crack growth behavior of 316LN weld metal in high-temperature pressurized water10.1016/j.corsci.2022.110169 ↗