Uniaxial low cycle fatigue behavior for pre-corroded 16MND5 bainitic steel in simulated pressurized water reactor environment
Source abstract
Abstract
Abstract The effects of uniaxial tension properties and low cycle fatigue behavior of 16MND5 bainitic steel cylinder pre-corroded in simulated pressurized water reactor (PWR) were investigated by fatigue at room temperature in air and immersion test system, scanning electron microscopy (SEM), energy disperse spectroscopy (EDS). The experimental results indicated that the corrosion fatigue lives of 16MND5 specimen were significantly affected by the strain amplitude and simulated PWR environments. The compositions of corrosion products were complexly formed in simulated PWR environments. The porous corrosion surface of pre-corroded materials tended to generate pits as a result of promoting contact area to the fresh metal, which promoted crack initiation. For original materials, the fatigue cracks initiated at inclusions imbedded in the micro-cracks. Moreover, the simulated PWR environments degraded the mechanical properties and low cycle fatigue behavior of 16MND5 specimens remarkably. Pre-corrosion of 16MND5 specimen mainly affected the plastic term of the Coffin-Manson equation.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Corrosion Behavior and Inhibition · Fatigue and fracture mechanics
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (32)
Show source-provided references
1. How would social acceptance affect nuclear power development? A study from China10.1016/j.jclepro.2015.04.049 ↗
2. Boric acid corrosion in the primary system of PWRs10.4028/www.scientific.net/AMR.1081.58 ↗
3. Effect of oxidation behavior on the corrosion fatigue crack initiation and propagation of 316LN austenitic stainless steel in high temperature water10.1016/j.msea.2015.03.026 ↗
4. Effect of mean stress and ratcheting strain on the low cycle fatigue behavior of a wrought 316LN stainless steel10.1016/j.msea.2016.09.053 ↗
5. The effect of LWR coolant environments on the fatigue life of reactor materials
6. Evaluation of effects of LWR coolant environments on fatigue life of carbon and low-alloy steels
7. Low-cycle fatigue of piping and pressure vessel steels in LWR environments10.1016/S0029-5493(97)00368-3 ↗
8. Environmental effect on fatigue strength of stainless steel in PWR primary water – role of crack growth acceleration in fatigue life reduction10.1016/j.ijfatigue.2013.05.008 ↗
9. Revised and new proposal of environmental fatigue life correction factor (Fen) for carbon and low-alloy steels and Nickel base alloys in LWR water environments
10. Strain-rate dependence of low cycle fatigue behavior in a simulated BWR environment10.1016/j.corsci.2004.07.037 ↗
11. Effects of mixed strain rates on low cycle fatigue behaviors of austenitic stainless steels in a simulated PWR environment10.1016/j.ijfatigue.2015.06.021 ↗
12. Environmental fatigue of metallic materials in nuclear power plants-a review of Korean test programs10.5516/NET.07.2013.040 ↗
13. Low cycle fatigue behavior of alloy 690 in simulated PWR water–Effects of dynamic strain aging and hydrogen10.1016/j.msea.2014.05.069 ↗
14. Low cycle fatigue behaviors of type 316LN austenitic stainless steel in 310 °C deaerated water–fatigue life and dislocation structure development10.1016/j.msea.2007.07.023 ↗
15. The effects of temperature and aeration on the corrosion of A508III low alloy steel in boric acid solutions at 25–95 °C10.1016/j.jnucmat.2016.08.009 ↗
16. Boric acid corrosion in the primary system of PWRs10.4028/www.scientific.net/AMR.1081.58 ↗
17. Strain-rate dependent fatigue behavior of 316LN stainless steel in high-temperature water10.1016/j.jnucmat.2017.03.040 ↗
18. Effects of loading factors on environmental fatigue behavior of low-alloy pressure vessel steels in simulated BWR water10.1016/j.nucengdes.2006.09.043 ↗
19. Corrosion fatigue behavior of low alloy steels under simulated BWR coolant conditions10.1016/j.jnucmat.2010.07.029 ↗
20. 15-Corrosion issues in pressurized water reactor (PWR) systems10.1533/9780857095343.5.473 ↗
21. Ductile to brittle transition of an A508 steel characterized by Charpy impact test: Part II: modeling of the Charpy transition curve10.1016/j.engfracmech.2004.03.010 ↗
22. Deformation studies from in situ SEM experiments of a reactor pressure vessel steel at room and low temperatures10.1016/j.jnucmat.2014.07.079 ↗
23. Experimental study of the phase transformation plasticity of 16MND5 low carbon steel under multiaxial loading10.1016/S0749-6419(01)00067-5 ↗
24. Temperature effects on low-cycle fatigue behavior of SA533B steel in simulated reactor coolant environments10.1016/j.matchemphys.2007.02.097 ↗
25. Low-cycle fatigue behaviors of two heats of SA508 Gr.1a low alloy steel in 310°C air and deoxygenated water–Effects of dynamic strain aging and microstructures10.1016/j.msea.2013.05.049 ↗
26. Corrosion in high-temperature and supercritical water and aqueous solutions: a view10.1016/S0896-8446(03)00031-7 ↗
27. Micromechanisms of fatigue crack nucleation and short crack growth in a low carbon steel under low cycle impact fatigue loading10.1016/S0142-1123(99)00031-6 ↗
28. Fatigue behavior of a harmonic structure designed austenitic stainless steel under uniaxial loading10.1016/j.msea.2017.09.063 ↗
29. A local criterion for cleavage fracture of a nuclear pressure vessel steel10.1007/BF02663302 ↗
30. Cavity formation from inclusions in ductile fracture of A508 steel10.1007/BF02648336 ↗
31. Overview of fatigue crack initiation in carbon and low-alloy steels in light water reactor environments10.1115/1.2883667 ↗
32. Review on effect of cyclic loading on environmental assisted cracking of alloy 600 in typical nuclear coolant waters10.1016/S0010-938X(01)00023-3 ↗