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    ISA MNTRNG MEAS I&C PERF NUC PWR PLNT-2014 Monitoring and Measuring I&C Performance in Nuclear Power Plants.pdf

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    ISA MNTRNG MEAS I&C PERF NUC PWR PLNT-2014 Monitoring and Measuring I&C Performance in Nuclear Power Plants.pdf

    1、MONITORING AND MEASURING I V = voltage; I = current).2 Fig. I.2 Data acquisition signal path for OLM .12 Fig. 1.1 Example of conventional sensors used in a PWR NPP 23 Fig. 1.2 Important pressure transmitters in a loop of a PWR plant24 Fig. 1.3 Bathtub curve showing different failure possibilities .2

    2、7 Fig. 1.4 OLM techniques categorized by source of data .33 Fig. 1.5 OLM applications versus sampling frequency 34 Fig. 1.6 OLM applications of static and dynamic data analysis 35 Fig. 1.7 Simplified diagram of chemical and volume control system components 37 Fig. 1.8 Actual noise data from a pressu

    3、re transmitter in an NPP and spectrum of one-hour record of this data .38 Fig. 1.9 Effect of sensing-line blockage on dynamic performance of a pressure transmitter .39 Fig. 1.10 Auto power spectral density containing vibration signatures of reactor internals 39 Fig. 1.11 Principle of LCSR test 42 Fi

    4、g. 1.12 Potential outcomes of TDR tests .44 Fig. 1.13 Integrated OLM system .46 Fig. 2.1 Slope and intercept of a calibration curve 50 Fig. 2.2 Schematics of two typical deadweight testers .50 Fig. 2.3 Zero shift .53 Fig. 2.4 Span shift with and without zero shift .54 Fig. 2.5 Hysteresis 54 Fig. 2.6

    5、 Principle of as-found and as-left calibration limits 57 Fig. 2.7 In-situ methods to verify the calibration of process instruments 58 Fig. 2.8 On-line monitoring data for four boiler level transmitters in an operating power plant 59 Fig. 3.1 Zero-order transfer function 62 Fig. 3.2 Frequency test pr

    6、inciple 63 Fig. 3.3 Equipment setup for PI testing .65 Fig. 3.4 Typical PI test transients 65 Fig. 3.5 PI test transients from response-time testing of force-balance pressure transmitters 67 Fig. 3.6 Noise data acquisition sequence .68 Fig. 3.7 Normal and skewed APDs of pressure transmitter noise si

    7、gnals .70 Fig. 3.8 Examples of PSDs of nuclear plant pressure transmitters .71 Fig. 3.9 Equipment setup for sensor response-time testing using the noise analysis technique .72 00-Frontmatter_final to ISA.indd 9 12/18/2013 2:32:55 PMx Monitoring and Measuring I (b) LCSR can determine the degree of bo

    8、nding of strain gauges to solid surfaces . 276 Fig. 14.13 LCSR for in situ testing of a thermocouple problem 276 Fig. 14.14 (a) RTD circuit; (b) TDR test results of the RTD circuit . 277 Fig. 14.15 Failed RTD detected by TDR 278 Fig. 14.16 Results of TDR monitoring of a thermocouple . 278 Fig. 14.17

    9、 (a) Capacitance measurement results for ten RTDs and dissipation factor calculations (for lead X1 to ground); (b) RTD circuit for the results shown in this table . 279 Fig. 14.18 (a) and (b) Screenshots of OLM software . 279 Fig. 14.19 (a) and (b) Data qualification results 279 Fig. 15.1 Primary lo

    10、op of a Pressurized Water Reactor (PWR) . 285 Fig. 15.2 Normal output of a process sensor with illustration of the DC and AC components of the output . 285 Fig. 15.3 Online monitoring applications of static and dynamic data analysis described in this chapter 287 Fig. 15.4 Online monitoring applicati

    11、ons versus sampling frequency 288 Fig. 15.5 Photograph of a nuclear plant sensing line with a partial blockage . 290 Fig. 15.6 Research results on the effect of sensing-line blockages on response time of nuclear plant pressure transmitters 291 Fig. 15.7 Example of a pressure transmitter filtering th

    12、e process noise . 293 Fig. 15.8 Examples of auto power spectral densities of nuclear plant pressure transmitters 293 Fig. 15.9 Simplified diagram of chemical and volume control system components . 297 Fig. 15.10 Normal operation of chemical and volume control system flow parameters .298 Fig. 15.11 C

    13、hemical and volume control system flow parameters at the onset of a reactor coolant pump seal leak . 298 Fig. 15.12 Auto power spectral density containing vibration signatures of reactor internals . 299 Fig. 15.13 Illustration of cross-correlation principle involving a neutron detector and a core-ex

    14、it thermocouple to determine transit time 301 Fig. 15.14 (a) Detector placement; (b) Typical detector noise data record . 302 Fig. 15.15 Frequency domain phase analysis to determine transit time 302 Fig. 15.16 Auto power spectral density of a neutron detector showing degradation due to an increase i

    15、n cable capacitance . 304 Fig. 15.17 Block diagram of on-line monitoring system . 306 Fig. 15.18 Dedicated data acquisition system for on-line monitoring . 307 Fig. 15.19 Data flow in separating the AC component of a sensor output from its DC component 308 Fig. 16.1 Dedicated data acquisition system 312 Fig. 16.2 Compressed data from a nuclear plant data historian 313 Fig. 16.3 Missing data record in measurements from a nuclear power plant . 313 00-Frontmatter_final to ISA.indd 13 12/18/2013 2:32:56 PM


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