CrN과 TiN 코팅을 적용한 증기 발생기 세관의 프레팅 마모에 대한 연구
A Study on Fretting Wear of CrN and TiN coated Tubes in a Nuclear Steam Generator
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The steam generator of nuclear power plant is composed with the bundles of long tubes. It is exposed fluid flow and weak in the vibration. The tubes are supported by anti-vibration bars. Due to vibration the wear damage is called as the fretting wear. It should be minimized for the safety of the plants. The hard coatings are very effective to reduce the amount of wear. The coatings of TiN and CrN are introduced in this study to protect the fretting surfaces. The tube-on-flat type tester was used for fretting wear tests. The results show that the wear amounts of the coated tubes were decreased depending on coating thickness. CrN was very effective to reduce the wear. In case of TiN the wear amounts were dependent on the coating thickness. Thick coating of TiN was very effective for wear resistance.
Abstract
The steam generator of nuclear power plant is composed with the bundles of long tubes. It is exposed fluid flow and weak in the vibration. The tubes are supported by anti-vibration bars. Due to vibration the wear damage is called as the fretting wear. It should be minimized for the safety of the plants. The hard coatings are very effective to reduce the amount of wear. The coatings of TiN and CrN are introduced in this study to protect the fretting surfaces. The tube-on-flat type tester was used for fretting wear tests. The results show that the wear amounts of the coated tubes were decreased depending on coating thickness. CrN was very effective to reduce the wear. In case of TiN the wear amounts were dependent on the coating thickness. Thick coating of TiN was very effective for wear resistance.
참고문헌 (4)
- C.E Taylor, "Vibration Damping in Multispan Heat Exchanger Tubes", J.of Pressure Vessel Technolohy, 120, pp.283~289 (1988)
- P.L.Ko, "Correlation of Support Impact Force and Fretting-Wear for a Heat Exchanger Tube", J.of Pressure Vessel Technology, 106, pp.69~77 (1984)
- S.H.Jeong, "Wear Transitions of Tube-Support Materials for a Nuclear Steam Generator Through Sliding Wear Test and Fretting Wear Test", Key Engineering Materials, 321, pp.430~433 (2006)
- S.H. Jeong, "Wear Transitions of Tube-Support components for Nuclear Steam Generator under Fretting Conditions", Key Engineering Materials, pp.1253~1266 (2006)