Accelerated Vibration Test of coolant channel components under simulated flow induced excitation
Creators
Description
Highlights: • The present study deals with the issue of loosening of the nut in the Grayloc joint due to flow induced vibration and fret in the feeder pipes in contact due to differential creep in the neighbouring channels. • Accelerated test has been done on the Grayloc joint on simulated flow induced vibration to study the effect of loosening of the nut. • In the present accelerated test, the component has not been led to failure (loosening) and an estimation of its service life has been approached based on the severity of test. • The inverse square law approach based on PSD comparison for severity of test have been used to correlate the actual operational hours and the Laboratory test hours to verify the loosening of the Grayloc nut for the present study. • By inverse power law approach, the minimum number of reactor-hours equivalent to 80 h of testing is 46,080 h (5.26 full power years). - Abstract: The present study outlines the accelerated testing procedure of a Grayloc joint assembly for possible loosening of its nut due to flow induced vibration. The concern of the Grayloc nut getting loosened in the absence of a lock nut due to flow induced vibration and the resulting fretting in the feeder pipes in contact due to differential creep in the neighbouring channels has been addressed here. The severity of the test was decided based on actual site measurement under different operating flow conditions and comparison of power spectral density (PSD). The laboratory test results were extrapolated for estimation of life of the component under operating condition using inverse power law approach. The uniqueness of the accelerated test is that the component under test has not been led to failure for assessing its operating life unlike conventional accelerated testing. From the tests and analysis, it was deduced that 80 h of accelerated laboratory testing was equivalent to 5.26 full power years (46,080 h) of the reactor operating life. The test duration was enough to obtain approval from the regulatory body to operate the reactor.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2016.01.019Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2016.01.019;
- PII
- S0029-5493(16)00030-3;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 300
- Journal Page Range
- p. 127-134
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48005643
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; COOLANTS; CREEP; EXCITATION; FAILURES; FLOW MODELS; JOINTS; PIPES; REACTOR SAFETY; SERVICE LIFE; SPECTRAL DENSITY; TESTING
- Descriptors DEC
- ENERGY-LEVEL TRANSITIONS; EVALUATION; FUNCTIONS; LIFETIME; MATHEMATICAL MODELS; MECHANICAL PROPERTIES; SAFETY; SIMULATION; SPECTRAL FUNCTIONS; TUBES
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.