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本文(ASTM D5144-2008(2016) Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants《核电厂使用防护涂层标准的标准指南》.pdf)为本站会员(orderah291)主动上传,麦多课文库仅提供信息存储空间,仅对用户上传内容的表现方式做保护处理,对上载内容本身不做任何修改或编辑。 若此文所含内容侵犯了您的版权或隐私,请立即通知麦多课文库(发送邮件至master@mydoc123.com或直接QQ联系客服),我们立即给予删除!

ASTM D5144-2008(2016) Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants《核电厂使用防护涂层标准的标准指南》.pdf

1、Designation: D5144 08 (Reapproved 2016)Standard Guide forUse of Protective Coating Standards in Nuclear PowerPlants1This standard is issued under the fixed designation D5144; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year

2、 of last revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon () indicates an editorial change since the last revision or reapproval.INTRODUCTIONProtective coatings (paints) have been used extensively in the nuclear industry to protect thesurfaces of faciliti

3、es and equipment from corrosion and contamination by radioactive nuclides inaccordance with ALARA. In the absence of a standard method of selecting, testing, and evaluatingcoatings, many sites evaluated paints by empirical tests to determine which were useful in theirparticular operation. Understand

4、ably, the methods of testing were not uniform throughout the industry.It has been very difficult, consequently, to compare the results obtained at one site with those obtainedat another. Standard tests whereby industrial (nuclear) users of paints systematically preparespecimens and subject them to s

5、elected evaluations, thus permitting uniform comparisons, areadvantageous, internationally as well as domestically.The designer of light water-moderated nuclear reactor systems must consider the possibility of aDesign Basis Accident (DBA) and the subsequent events which might lead to the release or

6、expulsionof a fraction of the fission-product inventory of the core to the reactor containment facility. Engineeredsafety features, principally a reactor containment facility, are provided to prevent the release of fissionproducts to the biological environment during and after this improbable event.

7、 The design, fabrication,quality assurance, and testing of these engineered safety features ensure reliable operation and safetyunder all anticipated conditions.Large areas of the reactor-containment facility are painted with safety-related coatings. If severedelamination, peeling, or flaking causes

8、 significant portions of the coating to be discharged into thecommon water reservoir, the performance of the safety systems could be seriously compromised bythe plugging of strainers, flow lines, pumps, spray nozzles, and core coolant channels. Safety-relatedcoatings may also exist outside of the re

9、actor-containment.This guide is the result of a comprehensive examination of the experience and data that have beendeveloped on protective coatings in the nuclear industry over approximately 50 years. Standardspertaining to nuclear coatings have historically been covered by ANSI N5.12, ANSI N101.2,

10、andANSI N101.4. Responsibility for updating, rewriting, and issuing appropriate ANSI replacementstandards has been transferred to ASTM, specifically ASTM Committee D33, on Protective Coatingand Lining Work for Power Generation Facilities.The objective of this guide is to provide a common basis on wh

11、ich protective coatings for thesurfaces of nuclear power generating facilities may be qualified and selected by reproducibleevaluation tests. This guide also provides guidance for application and maintenance of protectivecoatings. Quality assurance in the nuclear industry is a mandatory requirement

12、for all aspects ofsafety-related nuclear coatings work. Licensees of nuclear power plants are required to determine ifcoated surfaces are within the scope of 10CFR50.65, “The Maintenance Rule.” Any coated surfacesfound to be within the scope of 10CFR50.65 must satisfy the requirements of 10CFR50.65.

13、 ASMESection XI, Subsection IWE contains the requirements for periodic evaluation of the reactor-containment steel pressure boundary.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States11. Scope*1.1 This guide provides a common basis on wh

14、ich protec-tive coatings for the surfaces of nuclear power generatingfacilities may be qualified and selected by reproducible evalu-ation tests. This guide also provides guidance for applicationand maintenance of protective coatings. Under the environ-mental operating and accident conditions of nucl

15、ear powergeneration facilities, encompassing pressurized water reactors(PWRs) and boiling water reactors (BWRs), coating perfor-mance may be affected by exposure to any one, all, or acombination of the following conditions: ionizing radiation;contamination by radioactive nuclides and subsequent deco

16、n-tamination processes; chemical and water sprays; high-temperature high-pressure steam; and abrasion or wear.1.2 The content of this guide includes:SectionReferenced Documents 2Terminology 3Significance and Use 4Coating Material Testing 5Thermal Conductivity 5Surface Preparation, Coating Applicatio

17、n, and Inspection forShop and Field Work6Quality Assurance 7Keywords 81.2.1 In addition, this guide addresses technical topicswithin ANSI N5.12 and ANSI N101.2 that are covered byseparate ASTM standards, for example, surface preparation,(shop and field) and coating application, (shop and field).1.2.

18、2 Applicable sections of this guide and specific accep-tance criteria may be incorporated into specifications and otherdocuments where appropriate.21.3 The values stated in inch-pound units are to be regardedas standard. No other units of measurement are included in thisstandard.1.4 This standard do

19、es not purport to address all of thesafety concerns, if any, associated with its use. It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM Sta

20、ndards:3C177 Test Method for Steady-State Heat Flux Measure-ments and Thermal Transmission Properties by Means ofthe Guarded-Hot-Plate ApparatusD3843 Practice for Quality Assurance for Protective Coat-ings Applied to Nuclear FacilitiesD3911 Test Method for Evaluating Coatings Used in Light-Water Nuc

21、lear Power Plants at Simulated Design BasisAccident (DBA) ConditionsD3912 Test Method for Chemical Resistance of Coatingsand Linings for Use in Nuclear Power PlantsD4060 Test Method for Abrasion Resistance of OrganicCoatings by the Taber AbraserD4082 Test Method for Effects of Gamma Radiation onCoat

22、ings for Use in Nuclear Power PlantsD4227 Practice for Qualification of Coating Applicators forApplication of Coatings to Concrete SurfacesD4228 Practice for Qualification of Coating Applicators forApplication of Coatings to Steel SurfacesD4537 Guide for Establishing Procedures to Qualify andCertify

23、 Personnel Performing Coating and Lining WorkInspection in Nuclear FacilitiesD4538 Terminology Relating to Protective Coating andLining Work for Power Generation FacilitiesD4541 Test Method for Pull-Off Strength of Coatings UsingPortable Adhesion TestersD5139 Specification for Sample Preparation for

24、 Qualifica-tion Testing of Coatings to be Used in Nuclear PowerPlantsD5163 Guide for Establishing a Program for ConditionAssessment of Coating Service Level I Coating Systemsin Nuclear Power PlantsD7167 Guide for Establishing Procedures to Monitor thePerformance of Safety-Related Coating Service Lev

25、el IIILining Systems in an Operating Nuclear Power PlantD7230 Guide for Evaluating Polymeric Lining Systems forWater Immersion in Coating Service Level III Safety-Related Applications on Metal SubstratesD7234 Test Method for Pull-Off Adhesion Strength of Coat-ings on Concrete Using Portable Pull-Off

26、 Adhesion Tes-tersD7491 Guide for Management of Non-Conforming Coatingsin Coating Service Level I Areas of Nuclear Power PlantsE84 Test Method for Surface Burning Characteristics ofBuilding MaterialsE648 Test Method for Critical Radiant Flux of Floor-Covering Systems Using a Radiant Heat Energy Sour

27、ceE1461 Test Method for Thermal Diffusivity by the FlashMethodE1530 Test Method for Evaluating the Resistance to Ther-mal Transmission of Materials by the Guarded Heat FlowMeter Technique2.2 Other Standards:ANSI N5.12 Protective Coatings (Paints) for the NuclearIndustry4ANSI N101.2 Protective Coatin

28、gs (Paints) for Light WaterNuclear Reactor Containment Facilities4ANSI N101.4 Quality Assurance for Protective CoatingsApplied to Nuclear Facilities41This guide is under the jurisdiction of ASTM Committee D33 on ProtectiveCoating and Lining Work for Power Generation Facilities and is the directrespo

29、nsibility of Subcommittee D33.02 on Service and Material Parameters.Current edition approved Aug. 1, 2016. Published August 2016. Originallyapproved in 1991. Last previous edition approved in 2008 as D5144 081. DOI:10.1520/D5144-08R16.2CertainASTM standards are available in compilation form (which i

30、ncludes thisguide), as Compilation of ASTM Standards for Use of Protective Coating Standardsin Nuclear Power Plants for expedient reference and usage by personnel involvedin nuclear coating work.3For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at

31、serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.4Available from IHS, 321 Inverness Drive South, Englewood, CO 80112,http:/.D5144 08 (2016)2ASME Boiler and Pressure Vessel Code (BPVC) Section XI,Rules for Inservice

32、Inspection of Nuclear Power PlantComponents, Subsection IWE Requirements for ClassMC and Metallic Liners of Class CC Components ofLight-Water Cooled Power Plants5EPRI 1019157 Plant Support Engineering: Guideline onNuclear Safety-Related Coatings Revision 2 (formerlyTR-109937 and 1003102)610CFR50 App

33、endix B: Title 10, Chapter 1, Energy, Part 50,Domestic Licensing of Production and UtilizationFacilities, Appendix B, Quality Assurance Criteria forNuclear Power Plants and Fuel Reprocessing Plants710CFR50.65 Requirements for Monitoring the Effectivenessof Maintenance at Nuclear Power Plants7USNRC S

34、tandard Review Plan 6.1.2 Protective CoatingSystems (Paints) Organic Materials7USNRC Regulatory Guide 1.54 Regulatory/(1973) QualityAssurance Requirements for Protective Coatings Appliedto Water-Cooled Nuclear Power Plants, Revisions 0, 1,and 27USNRC Regulatory Guide 8.8 Information Relevant to En-s

35、uring that Occupational Radiation Exposures At NuclearPower Stations Will BeAs LowAs Is ReasonablyAchiev-able73. Terminology3.1 DefinitionsDefinitions for use with this guide areshown in Terminology D4538 or other applicable standards.4. Significance and Use4.1 This guide addresses the concerns of R

36、egulation Guide1.54 and USNRC Standard Review Plan 6.1.2, and the replace-ment of ANSI Standards N5.12, N101.2, and N101.4. Thisguide covers coating work on previously coated surfaces aswell as bare substrates. This guide applies to all coating workin Coating Service Level I and III areas (that is,

37、safety-relatedcoating work). Applicable sections of this guide may also beused to evaluate and select protective coatings for CoatingService Level II areas where deemed appropriate by thelicensee.4.2 The testing referenced in this guide is particularlyappropriate for safety-related coatings inside t

38、he reactor-containment. Other test methods may be used for assessing thesuitability for service of safety-related coatings outside thereactor-containment. Criteria for qualification and performancemonitoring of Coating Service Level III coatings shall beaddressed in job specifications. Guidance for

39、selecting andperformance monitoring of Coating Service Level III coatingsis provided Guides D7230 and D7167 respectively, and Sec-tions 4.4 and 4.5 of EPRI 1019157 (formerly TR-109937 and1003102.).4.3 Users of this guide must ensure that coatings workcomplies not only with this guide, but also with

40、the licenseesplant-specific quality assurance program and licensing com-mitments.4.4 Safety-Related Coatings:4.4.1 The qualification of coatings for Coating ServiceLevels I and III are different even though they are bothsafety-related. This guide provides the minimum requirementsfor qualifying Coati

41、ng Service Level I coatings and alsoprovides guidance for additional qualification tests that may beused to evaluate Coating Service Level I coatings. This guidealso provides guidance concerning selection of Coating ServiceLevel III coatings.4.4.2 Coating Service Level I Coatings:4.4.2.1 All Coating

42、 Service Level I coatings must be resis-tant to the effects of radiation and must be DBA qualified. Thetest specimens shall be prepared, irradiated and DBA testedand evaluated in accordance with the requirements of:(a) Test Method D3911 or plant specific requirements asapplicable,(b) Test Method D40

43、82, and(c) Specification D5139.4.4.2.2 In addition to the requirements of 4.4.2.1, CoatingService Level I coatings may be evaluated for additionalqualities or may require application controls when deemedapplicable by the job specifications or licensing commitments.The following documents provide gui

44、dance for application,possible additional testing or for the further evaluation ofCoating Service Level I coatings when applicable:(a) Test Method C177,(b) Practice D3843,(c) Test Method D3912,(d) Test Method D4060,(e) Practice D4227,(f) Practice D4228,(g) Guide D4537,(h) Test Method D4541,(i) Test

45、Method E84,(j) Test Method E648,(k) Test Method E1461, and(l) Test Method E1530.4.4.2.3 Condition assessment and management of CoatingService Level I coatings is also required by the licensee tomaintain the coatings following the initial application andsubsequent repairs. The following documents pro

46、vide guidancefor the monitoring and management of the Coating ServiceLevel I coatings:(a) Guide D5163 and(b) Guide D7491.4.4.3 Coating Service Level III Coatings:4.4.3.1 Coating Service Level III coatings must be evalu-ated for use in accordance with the requirements of plantlicensing commitments an

47、d the job specifications. CoatingService Level III coatings may include linings used in areassuch as service water systems, essential cooling water heatexchanger heads and emergency diesel generator air intakes.There are no specific testing or qualification requirementsincluded in this guide for Coa

48、ting Service Level III coatings or5Available from American Society of Mechanical Engineers (ASME), ASMEInternational Headquarters, Three Park Ave., New York, NY 10016-5990, http:/www.asme.org.6Available from EPRI Distribution Center, 207 Coggins Drive, P.O. Box 23205,Pleasant Hills, CA 94523, http:/

49、.7Available from U.S. Government Printing Office, Superintendent ofDocuments, 732 N. Capitol St., NW, Washington, DC 20401-0001, http:/www.access.gpo.gov.D5144 08 (2016)3linings. Testing and evaluation of Coating Service Level IIIcoatings should be conducted as necessary to ensure that thecoatings are suitable for the specific service environment. Thefollowing documents provide guidance for testing andinspection, which the licensee may consider when preparingjob specifications for Coating Service Level III coatings orlinings:(a) Test Method D4541,(b)

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