BS IEC IEEE 62582-3-2013 Nuclear power plants Instrumentation and control important to safety Electrical equipment condition monitoring methods Elongation at break《核电站 对安全重要的仪表监测和控.pdf

1、raising standards worldwideNO COPYING WITHOUT BSI PERMISSION EXCEPT AS PERMITTED BY COPYRIGHT LAWBSI Standards PublicationNuclear power plants Instrumentation and controlimportant to safety Electrical equipment conditionmonitoring methodsPart 3: Elongation at breakBS IEC/IEEE 62582-3:2012National fo

2、rewordThis British Standard is the UK implementation of IEC/IEEE 62582-3:2012.The UK participation in its preparation was entrusted to Technical CommitteeNCE/8, Reactor instrumentation.A list of organizations represented on this committee can be obtained onrequest to its secretary.This publication d

3、oes not purport to include all the necessary provisions of acontract. Users are responsible for its correct application. The British Standards Institution 2013Published by BSI Standards Limited 2013ISBN 978 0 580 64472 6ICS 27.120.20Compliance with a British Standard cannot confer immunity fromlegal

4、 obligations.This British Standard was published under the authority of the StandardsPolicy and Strategy Committee on 31 January 2013.Amendments issued since publicationAmd. No. Date Text affectedBRITISH STANDARDBS IEC/IEEE 62582-3:2012IEC/IEEE 62582-3 Edition 1.0 2012-11 INTERNATIONAL STANDARD NORM

5、E INTERNATIONALE Nuclear power plants Instrumentation and control important to safety Electrical equipment condition monitoring methods Part 3: Elongation at break Centrales nuclaires de puissance Instrumentation et contrle-commande importants pour la sret Mthodes de surveillance de ltat des matriel

6、s lectriques Partie 3: Allongement la rupture INTERNATIONAL ELECTROTECHNICAL COMMISSION COMMISSION ELECTROTECHNIQUE INTERNATIONALE T ICS 27.120.20 PRICE CODE CODE PRIX ISBN 978-2-83220-424-5 Warning! Make sure that you obtained this publication from an authorized distributor. Attention! Veuillez vou

7、s assurer que vous avez obtenu cette publication via un distributeur agr. BS IEC/IEEE 62582-3:2012 2 62582-3 IEC/IEEE:2012 CONTENTS FOREWORD . 4 INTRODUCTION . 6 1 Scope and object 8 2 Terms and definitions . 8 3 General description 9 4 Applicability and reproducibility 9 5 Measurement procedure . 9

8、 5.1 Stabilisation of the polymeric materials 9 5.2 Sampling . 9 5.2.1 General . 9 5.2.2 Sample requirements . 10 5.3 Specimen preparation . 10 5.3.1 General . 10 5.3.2 Dumb-bell specimens 11 5.3.3 Tubular specimens 11 5.3.4 O-ring specimens 11 5.4 Instrumentation . 11 5.4.1 Tensile test machine 11

9、5.4.2 Calibration . 11 5.4.3 Use of extensometers 11 5.5 Tensile elongation measurement method. 12 5.5.1 Conditioning 12 5.5.2 Dimensions of test specimens . 12 5.5.3 Clamping . 12 5.5.4 Testing speed 12 5.5.5 Recording data 13 5.5.6 Calculation of results . 13 5.6 Measurement report 14 Annex A (inf

10、ormative) Shape and dimensions of test specimens 15 Annex B (informative) Preparation of test specimens from cable samples 18 Annex C (informative) Typical load versus elongation curves . 20 Annex D (normative) Dies for cutting dumb-bell specimens 22 Annex E (informative) Example of a measurement re

11、port from tensile elongation measurements 23 Bibliography 24 Figure A.1 Shape of dumb-bell specimens . 15 Figure A.2 Fitting end tabs to tubular specimens 16 Figure A.3 Fitting soft inserts to tubular specimens 17 Figure A.4 Mounting of O-ring specimens in the test machine 17 Figure C.1 Typical load

12、-elongation curves . 20 Figure C.2 Typical load-time curve with a slipping specimen 21 Figure D.1 Suitable cutters for dumb-bell specimens 22 BS IEC/IEEE 62582-3:201262582-3 IEC/IEEE:2012 3 Table 1 Testing speeds for elongation measurements 12 Table A.1 Recommended dimensions for dumb-bell specimens

13、 . 15 BS IEC/IEEE 62582-3:2012 4 62582-3 IEC/IEEE:2012 INTERNATIONAL ELECTROTECHNICAL COMMISSION _ NUCLEAR POWER PLANTS INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY ELECTRICAL EQUIPMENT CONDITION MONITORING METHODS Part 3: Elongation at break FOREWORD 1) The International Electrotechnical Commiss

14、ion (IEC) is a worldwide organization for standardization comprising all national electrotechnical committees (IEC National Committees). The object of IEC is to promote international co-operation on all questions concerning standardization in the electrical and electronic fields. To this end and in

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28、eferences cited in this publication. Use of the referenced publications is indispensable for the correct application of this publication. 9) Attention is drawn to the possibility that implementation of this IEC/IEEE Publication may require use of material covered by patent rights. By publication of

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31、any patent rights, and the risk of infringement of such rights, is entirely their own responsibility. BS IEC/IEEE 62582-3:201262582-3 IEC/IEEE:2012 5 International Standard IEC/IEEE 62582-3 has been prepared by subcommittee 45A: Instrumentation and control of nuclear facilities, of IEC technical com

32、mittee 45: Nuclear instrumentation, in cooperation with the Nuclear Power Engineering Committee of the Power & Energy Society of the IEEE1, under the IEC/IEEE Dual Logo Agreement. This publication is published as an IEC/IEEE Dual Logo standard. The text of this standard is based on the following IEC

33、 documents: FDIS Report on voting 45A/887/FDIS 45A/891/RVD Full information on the voting for the approval of this standard can be found in the report on voting indicated in the above table. International standards are drafted in accordance with the rules given in the ISO/IEC Directives, Part 2. A l

34、ist of all parts of IEC/IEEE 62582, under the general title Nuclear power plants Instrumentation and control important to safety Electrical equipment condition monitoring methods, can be found on the IEC website. The IEC Technical Committee and IEEE Technical Committee have decided that the contents

35、 of this publication will remain unchanged until the stability date indicated on the IEC web site under “http:/webstore.iec.ch“ in the data related to the specific publication. At this date, the publication will be reconfirmed, withdrawn, replaced by a revised edition, or amended. 1A list of IEEE pa

36、rticipants can be found at the following URL: http:/standards.ieee.org/downloads/62582-3/62582-3-2012/62582-3-2012_wg-participants.pdf. BS IEC/IEEE 62582-3:2012 6 62582-3 IEC/IEEE:2012 INTRODUCTION a) Technical background, main issues and organisation of the standard This part of this IEC/IEEE stand

37、ard specifically focuses on elongation at break methods for condition monitoring for the management of ageing of electrical equipment installed in nuclear power plants. The method is primarily suited to samples taken from equipment that are based on thermoplastic or elastomeric polymers. This part o

38、f IEC/IEEE 62582 is the third part of the IEC/IEEE 62582 series. It contains detailed descriptions of condition monitoring based on elongation at break measurements. The IEC/IEEE 62582 series is issued with a joint logo which makes it applicable to management of ageing of electrical equipment qualif

39、ied to IEEE as well as IEC Standards. Historically, IEEE Std 323-2003 introduced the concept and role that condition based qualification could be used in equipment qualification as an adjunct to qualified life. In equipment qualification, the condition of the equipment for which acceptable performan

40、ce was demonstrated is the qualified condition. The qualified condition is the condition of equipment, prior to the start of a design basis event, for which the equipment was demonstrated to meet the design requirements for the specified service conditions. Significant research has been performed on

41、 condition monitoring techniques and the use of these techniques in equipment qualification as noted in NUREG/CR-6704, vol.2 (BNL-NUREG-52610) and JNES-SS-0903, 2009. It is intended that this IEC/IEEE standard be used by test laboratories, operators of nuclear power plants, systems evaluators and li

42、censors. b) Situation of the current Standard in the structure of the IEC SC 45A standard series Part 3 of IEC/IEEE 62582 is the third level IEC SC 45A document tackling the specific issue of application and performance of elongation at break measurements in management of ageing of electrical instru

43、ment and control equipment in nuclear power plants. Part 3 of IEC/IEEE 62582 is to be read in association with part 1 of IEC/IEEE 62582, which provides requirements for application of methods for condition monitoring of electrical equipment important to safety of nuclear power plants. For more detai

44、ls on the structure of the IEC SC 45A standard series, see item d) of this introduction. c) Recommendations and limitations regarding the application of this Standard It is important to note that this Standard establishes no additional functional requirements for safety systems. d) Description of th

45、e structure of the IEC SC 45A standard series and relationships with other IEC documents and other bodies documents (IAEA, ISO) The top-level document of the IEC SC 45A standard series is IEC 61513. It provides general requirements for I&C systems and equipment that are used to perform functions imp

46、ortant to safety in NPPs. IEC 61513 structures the IEC SC 45A standard series. IEC 61513 refers directly to other IEC SC 45A standards for general topics related to categorization of functions and classification of systems, qualification, separation of systems, defence against common cause failure,

47、software aspects of computer-based systems, BS IEC/IEEE 62582-3:201262582-3 IEC/IEEE:2012 7 hardware aspects of computer-based systems, and control room design. The standards referenced directly at this second level should be considered together with IEC 61513 as a consistent document set. At a thir

48、d level, IEC SC 45A standards not directly referenced by IEC 61513 are standards related to specific equipment, technical methods, or specific activities. Usually these documents, which make reference to second-level documents for general topics, can be used on their own. A fourth level extending th

49、e IEC SC 45 standard series, corresponds to the Technical Reports which are not normative. IEC 61513 has adopted a presentation format similar to the basic safety publication IEC 61508 with an overall safety life-cycle framework and a system life-cycle framework. Regarding nuclear safety, it provides the interpretation of the general requirements of IEC 61508-1, IEC 61508-2 and IEC 61508-4, for the nuclear application sector, regarding nuclear safety. In thi