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Chen, M.H.; Lee, C.D.; Ma, C.C.; Shieh, D.J.
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 22004
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 22004
AbstractAbstract
[en] An on-line automatic sensor response time analysis system in Taipower's Maanshan PWR nuclear power plant is presented. The algorithm applied in the system is the noise analysis technique which is an indirect method of determining sensor response time. This technique includes the power spectral density analysis and the autoregressive analysis methods. The system can also be used for long-term surveillance of sensor performance trends and cross-comparison of redundant sensors for predictive maintenance purposes. (author)
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Nuclear Energy Society, Taipei, Taiwan (China); American Nuclear Society (United States); American Society of Mechanical Engineers (United States); Atomic Energy Society of Japan (Japan); Canadian Nuclear Society (Canada); Korean Nuclear Society (Korea, Republic of); 814 p; 2004; p. 32D1-32D6; 4. international topical meeting on nuclear thermal hydraulics, operations and safety; Taipei, Taiwan (China); 5-8 Apr 1994; This record replaces 35095591; 2 refs, 4 figs, 1 tab
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