Turbulent flow-induced vibration in nuclear fuel may cause fretting wear of fuel rod at grid support locations. An advanced nuclear fuel for Korean PWR standard nuclear power plants (KSNPs), has been developed to get higher performance comparing to the current fuel considering the safety and economy. One of the significant features of the advanced fuel is the conformal shape in mid grid springs and dimples, which are developed to diminish the fretting wear failure. Long-term hydraulic tests have been performed to evaluate the fretting wear of the fuel rod with the conformal springs and dimples. Wear volume is a measure to predict the fretting wear performance. The shapes of a lot of scars are non-uniform such as wedge shapes, and axially non-symmetric shapes, etc., depending on the contact angle between fuel rod and springs/dimples. In addition, conformal springs and dimples make wear scars wide and thin comparing to conventional ones with convex shape. It is found that wear volumes of these kinds of non-uniform wear scars are over-predicted when the traditionally used wear depth-dependent volume calculation method is employed. In order to predict wear volume more accurately, therefore, the measuring system with high accuracy has been used and verified by the known wear volumes of standard specimens. The wear volumes of the various wear scars have been generated by the measuring system and used for predicting the fretting wear-induced failure time. Based on new evaluation method, it is considered that the fretting wear-induced fuel failure duration with this conformal grid has increased up to 8 times compared to the traditionally used wear depth-dependent volume calculation method.
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ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference
July 23–27, 2006
Vancouver, BC, Canada
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
0-7918-4755-1
PROCEEDINGS PAPER
An Evaluation of Fuel Rod Fretting Wear in Spacer Grid With Conformal Shape
Young Ki Jang,
Young Ki Jang
Korea Nuclear Fuel Company, Ltd., Daejeon, Korea
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Nam Kyu Park,
Nam Kyu Park
Korea Nuclear Fuel Company, Ltd., Daejeon, Korea
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Jae Ik Kim,
Jae Ik Kim
Korea Nuclear Fuel Company, Ltd., Daejeon, Korea
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Kyu Tae Kim,
Kyu Tae Kim
Korea Nuclear Fuel Company, Ltd., Daejeon, Korea
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Chong Chul Lee,
Chong Chul Lee
Korea Nuclear Fuel Company, Ltd., Daejeon, Korea
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Kyu Zong Cho
Kyu Zong Cho
Chonnam National University, Gwangju, Korea
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Young Ki Jang
Korea Nuclear Fuel Company, Ltd., Daejeon, Korea
Nam Kyu Park
Korea Nuclear Fuel Company, Ltd., Daejeon, Korea
Jae Ik Kim
Korea Nuclear Fuel Company, Ltd., Daejeon, Korea
Kyu Tae Kim
Korea Nuclear Fuel Company, Ltd., Daejeon, Korea
Chong Chul Lee
Korea Nuclear Fuel Company, Ltd., Daejeon, Korea
Kyu Zong Cho
Chonnam National University, Gwangju, Korea
Paper No:
PVP2006-ICPVT-11-93546, pp. 1571-1575; 5 pages
Published Online:
July 23, 2008
Citation
Jang, YK, Park, NK, Kim, JI, Kim, KT, Lee, CC, & Cho, KZ. "An Evaluation of Fuel Rod Fretting Wear in Spacer Grid With Conformal Shape." Proceedings of the ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference. Volume 4: Fluid Structure Interaction, Parts A and B. Vancouver, BC, Canada. July 23–27, 2006. pp. 1571-1575. ASME. https://doi.org/10.1115/PVP2006-ICPVT-11-93546
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