Experimental Study on the Wear Behavior of Nuclear Fuel Rod in High Temperature Water Environment

Abstract:

In this study, the variation of spring characteristics with increasing temperature was examined and the effect of their variations on the wear behavior of a nuclear fuel rod in both room and high temperature (300°C) water conditions was evaluated. From the results of the load-displacement tests, the spring stiffness was remarkably varied with increasing temperature. The results of the wear tests indicated that the wear damages are decreased at high temperature water when compared with the room temperature result. These results indicated that the removal mechanisms of wear debris at high temperature water are dependent on not only the formation of the wear particle layer but also on the changed contact conditions such as the contact length or area due to the stiffness drops.

• Periodical: Key Engineering Materials (Volumes 297-300)
• Pages: 1395-1400
• DOI: https://doi.org/10.4028/www.scientific.net/KEM.297-300.1395
• Online since: November 2005
• Authors: Young Ho Lee, Hyung Kyu Kim, Youn Ho Jung
• Keywords: Fretting Wear, High Temperature Water, Load-Displacement Curves, Nuclear Fluel Rod, Spacer Grid

References

[1] Y.H. Lee, I.S. Kim, S.S. Kang and H.D. Jung: Wear Vol. 250 (2000), p.719.

[2] Y.H. Lee and I.S. Kim: Wear Vol. 253 (2002), p.438.

[3] Y.H. Lee, H.K. Kim and Y.H. Jung: KSTLE International Journal Vol. 4 (2003), p.31.

[4] Y.H. Lee, H.K. Kim and Y.H. Jung: 14 th Int' Colloquium Tribology Vol. II (2004), p.929.

[5] User's manual for Matrox Inspector® Ver. 2. 2 (Matrox Inc., USA 1997).

[6] Y.H. Lee, H. K, Kim and Y.H. Jung: Proceedings of the of 2004 International Meeting on LWR Fuel Performance (2004).

[7] A. Iwabuchi: Wear Vol. 151 (1991), p.301.