DIN 25475-2-2009 Nuclear facilities - Operational monitoring - Part 2 Vibration monitoring for early detection of changes in the vibrational behavior of the primary coolant circuit.pdf
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1、May 2009DEUTSCHE NORM Normenausschuss Materialprfung (NMP) im DINDIN-SprachendienstEnglish price group 22No part of this translation may be reproduced without prior permission ofDIN Deutsches Institut fr Normung e. V., Berlin. Beuth Verlag GmbH, 10772 Berlin, Germany,has the exclusive right of sale
2、for German Standards (DIN-Normen).ICS 27.120.20!$a(M“1620542www.din.deDDIN 25475-2Nuclear facilities Operational monitoring Part 2: Vibration monitoring for early detection of changes in thevibrational behavio r of the primary coolant circuit in pressurized water reactorsEnglish translation of DIN 2
3、5475-2:2009-05Kerntechnische Anlagen Betriebsberwachung Teil 2: Schwingungsberwachung zur frhzeitigen Erkennung von nderungen imSchwingungsverhalten des Primrkreises von DruckwasserreaktorenEnglische bersetzung von DIN 25475-2:2009-05Installations nuclaires Surveillance en exploitation Partie 2: Sur
4、veillance des vibrations en vue de la dtection prcoce de modifications ducomportement vibratoire du circuit primaire de racteurs eau sous pressionTraduction anglaise de DIN 25475-2:2009-05SupersedesDIN 25475-2:2001-08www.beuth.deDocument comprises pages5807.10u DIN 25475-2:2009-05 2 A comma is used
5、as the decimal marker. Contents Page Foreword3 1 Scope 3 2 Normative references3 3 Terms and definitions .4 4 Description of the monitoring technology4 5 Requirements of the vibration monitoring system 7 5.1 Basic structure and interpretation criteria7 5.2 Data acquisition .9 5.2.1 General9 5.2.2 Se
6、lecting locations and installing the transducers and cables9 5.2.3 Example of a data acquisition 12 5.3 Signal conditioning .18 5.4 Signal analysis.19 5.5 Signal presentation .19 5.5.1 Display unit 19 5.5.2 Recording .19 5.6 Calibration 19 5.6.1 General19 5.6.2 Calibration unit 20 6 Commissioning20
7、6.1 General20 6.2 System checks.20 6.3 Measurements during commissioning of the reactor20 7 Performance of monitoring 21 7.1 General21 7.2 Prerequisites 21 7.3 Measurements22 7.3.1 General22 7.3.2 Reference measurements.22 7.3.3 Operational measurements 23 7.3.4 Identification 23 7.4 Monitoring 23 7
8、.4.1 Selecting a comparative measurement.23 7.4.2 Determination and evaluation of changes 24 7.5 Test of the monitoring system .28 7.5.1 General28 7.5.2 Test during fuel outage of the plant 29 7.5.3 Test during operation of the reactor29 8 Documentation.29 Annex A (informative) Vibration monitoring,
9、 Example 1.31 A.1 General31 A.2 Monitoring of the components of the primary circuit and reactor pressure vessel internals31 A.3 Frequency-selective monitoring of the shaft vibrations of the main coolant pumps 33 Annex B (informative) Vibration monitoring, Example 2.43 B.1 Monitoring the components o
10、f the primary circuit and reactor pressure vessel internals .43 B.2 Frequency-selective monitoring of shaft vibrations in the main coolant pumps.45 Annex C (informative) Example of signal trends of a fractured shaft .56 Bibliography58 DIN 25475-2:2009-05 3 Foreword This document has been prepared by
11、 NA 062-07-48 AA Betriebsberwachung Kerntechnik. Requirements with regard to the vibration monitoring system, its commissioning, the monitoring process, and documentation are specified in order to detect changes in the vibrational behaviour of the components of the primary circuit, the reactor press
12、ure vessel internals, and the main coolant pump shafts at an early enough stage so that there is sufficient time to analyze the changes in vibration and thus identify any imminent defects or damage and ensure aimed inspections. Based on KTA 3201.4, the standard is titled “Operational monitoring”. DI
13、N 25475 Nuclear facilities Operational monitoring comprises the following: Part 1: Monitoring of structure-borne sound for loose parts detection Part 2: Vibration monitoring for early detection of changes in the vibrational behaviour of the primary coolant circuit in pressurized water reactors Annex
14、es A, B and C are informative. Amendments This standard differs from DIN 25475-2:2001-08 as follows: a) Monitoring of main coolant pump shafts has been added; b) Modifications have been made as a result of operational experience; c) The definition of terms has been modified; d) Figures have been mod
15、ified; e) Annexes A and B have been modified, Annex C has been added. Previous editions DIN 25475-2: 2001-08 1 Scope This standard applies to procedures for early detection of changes in the vibration of the components of the primary circuit, the reactor pressure vessel internals, and main coolant p
16、ump shafts of pressurized water reactors. The monitoring system used in this respect is an operational facility that does not require a layout in accordance with KTA 3501. This standard shall not be applied to procedures for monitoring maximum shaft deflections of main coolant pumps. For details reg
17、arding maximum shaft deflections see DIN ISO 7919-1 and VDI 2059 Part 5. 2 Normative references The following referenced documents are indispensable for the application of this document. For dated references, only the edition cited applies. For undated references, the latest edition of the reference
18、d document (including any amendments) applies. DIN 25404:1991-01, Nuclear technology Symbols KTA 3204, Reactor pressure vessel internals KTA 3501, Reactor protection systems and monitoring facilities of the safety system DIN 25475-2:2009-05 4 3 Terms and definitions For the purposes of this document
19、, the following terms and definitions apply. 3.1 attention thresholds values that shall be established specifically in respect to the feature to be monitored and, if exceeded, require additional measures 3.2 peak identifiable part of the curve in a characteristic function that is characterized by a
20、local maximum and a definite width 3.3 frequency band frequency range that is defined by an upper and lower frequency 3.4 magnitude value of the auto power density spectrum relating to a frequency 3.5 resonance frequencies natural frequencies of components of the primary circuit modified by damping
21、and coupling 3.6 type of vibration time- and location-based vibration form of a component relating to the respective resonance frequency 4 Description of the monitoring technology The vibration monitoring system is used to detect changes in the vibration of reactor pressure vessel internals, additio
22、nal primary circuit components and main coolant pump shafts at an early stage. The parameters decisive for the vibration are masses, spring constants, dampings, excitation forces, gaps, and stops. The vibration behaviour is primarily recorded by transducers for the measurement of mechanical vibratio
23、n on the outside of the pressure retaining boundary, of the neutron flux noise, of pressure fluctuation, and of main coolant pump shaft vibration. These measurands provide information that are either meaningful by themselves, partly superimpose each other, or complement each other. The basic connect
24、ions of vibration excitation and available measurands as well as any information derived from them are outlined in Figure 1. DIN 25475-2:2009-05 5 Figure 1 Basic vibration-related connections at the primary circuit DIN 25475-2:2009-05 6 Figure 2 Examples of signals in the time domain and correspondi
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