- Volume 41 Issue 5
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Acceleration Test Method for Failure Prediction of the End Cap Contact Region of Sodium Cooled Fast Reactor Fuel Rod
소듐냉각 고속로 연료봉단의 접촉부 손상예측을 위한 가속시험 방법
- Kim, Hyung-Kyu (Korea Atomic Energy Research Institute) ;
- Lee, Young-Ho (Korea Atomic Energy Research Institute) ;
- Lee, Hyun-Seung (Korea Atomic Energy Research Institute) ;
- Lee, Kang-Hee (Korea Atomic Energy Research Institute)
- Received : 2016.08.25
- Accepted : 2016.12.30
- Published : 2017.05.01
This paper reports the results of an acceleration test to predict the contact-induced failure that could occur at the cylinder-to-hole joint for the fuel rod of a sodium-cooled fast reactor (SFR). To incorporate the fuel life of the SFR currently under development at KAERI (around 35,000 h), the acceleration test method of reliability engineering was adopted in this work. A finite element method was used to evaluate the flow-induced vibration frequency and amplitude for the test parameter values. Five specimens were tested. The failure criterion during the life of the SFR fuel was applied. The S-N curve of the HT-9, the material of concern, was used to obtain the acceleration factor. As a result, a test time of 16.5 h was obtained for each specimen. It was concluded that the
Acceleration Test;Contact-induced Failure Prediction;Sodium Cooled Fast Reactor Fuel;Fatigue Life
- Kim, S.-H., 2004, "Tensile Properties of 12Cr-1MoW Martensitic Stainless Steel," KAERI Internal Report.
- Simulia, ABAQUS version 6.14 User's Manual.
- Kim, H.-K., Kim, S.-J., Yoon, K.-H., Kang, H.-S., Song, K.-N., 2001, "Fretting Wear of Laterally Supported Tube," Wear, Vol. 250, pp. 535-543. https://doi.org/10.1016/S0043-1648(01)00634-2
- Reliability Evaluation Center, Korea Institute of Machinery and Materials, 2016, Reliability Engineering of Machinery and Automobile Industry, Sigma Press, pp. 422-479.
- Fuchs, H.O. and Stephens, R.I., 1980, Metal Fatigue in Engineering, Wiley, New York.
- Haidyrah, A.S.R., 2015, Characterization of Bending Fatigue Mini-specimen for Nuclear Materials, PhD Thesis, Missouri University of Science and Technology, p. 55.
- Origin Lab, Origin version 9.