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AbstractAbstract
[en] Nuclear reactors have been operating and producing useful electricity for many years. Within the last few years, several plants have found cracks in the reactor coolant pump shaft near the thermal barrier. The modal method and results described herein show the analytical results of using a Modal Analysis test method to determine the presence, size, and location of a shaft crack. The authors have previously demonstrated that the test method can analytically and experimentally identify shaft cracks as small as five percent (5%) of the shaft diameter. Due to small differences in material property distribution, the attempt to identify cracks smaller than 3% of the shaft diameter has been shown to be impractical. The rotor dynamics model includes a detailed motor rotor, external weights and inertias, and realistic total support stiffness. Results of the rotor dynamics model have been verified through a comparison with on-site vibration test data
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Electric Power Research Inst., Palo Alto, CA (United States); EPRI Nondestructive Evaluation Center, Charlotte, NC (United States); 397 p; May 1991; p. 5.1-5.32; 1990 main coolant pump diagnostics (MCPs) workshop; New Orleans, LA (United States); 17-18 Apr 1990; CONF-9004313--; Research Reports Center, PO Box 50490, Palo Alto, CA 94303
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Report
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Conference
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