Frictional wear characteristics of nickel-based alloy and reactor material in pressure vessel reactor
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Wei Zhang
Abstract
The reactor pressure vessel was contact sealed with a double-channel O-ring made of Inconel 718 alloy and nuclear power material SA508. The fretting wear characteristics of Inconel 718 O-tube and SA508 plate friction pair were tested by fretting wear testing machine to explore the failure mechanism of reactor pressure vessel seal system. The test conditions are as follows: normal temperature, normal loads of 10, 20, and 40 N, displacement amplitude of 600 μm, the number of cycles of 10,000, and frequency of 4 Hz. Results show that the coefficient of friction (COF) increased with increasing normal force. Significant material losses were detected during the relative sliding of the contact surface of SA508. A large number of abrasive dust accumulated at the edge of the contact zone, forming a large number of oxides. During the friction of Inconel 718 O-ring, plastic deformation occurred, and a plastic flow layer was formed. The plastic deformation flow at the contact point formed an adhesive connection point, producing adhesive wear and oxidative wear. The wear mechanism was characterized by the combination of oxidative wear and abrasive wear.
Funding source: National Natural Science Foundation of China
Award Identifier / Grant number: 51605437
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: This work was funded by National Natural Science Foundation of China (51605437).
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
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Artikel in diesem Heft
- Frontmatter
- A study of RCS depressurization strategy of CPR1000 SAMG
- Drones application scenarios in a nuclear or radiological emergency
- Safety analysis for integrity enhancement in nuclear power plants (NPPs) in case of seashore region site
- Frictional wear characteristics of nickel-based alloy and reactor material in pressure vessel reactor
- Improving FNMC for the matrix effect of spherical shell plutonium samples
- Calculation of core neutronic parameters in electron accelerator driven subcritical TRIGA reactor
- Preliminary study on TRU transmutation in VVER-1000 fuel assembly using MCNP6
- Research on the application of 22Na radiolocation detection technology in advanced manufacturing process control
- Coupling MCNP6/ANSYS codes to calculate axial temperature and power distribution in a VVER-1000 fuel assembly
- Experimental and theoretical investigation of forced convection heat transfer with CNTs and CuO water based nano-fluids
- Thermal hydraulic characteristics of silicon irradiation in a typical MTR reactor
- Photon dosimetry using selective data sampling with Particle Swarm optimization algorithm based on NaI(Tl) scintillation detector
- Calendar of events
