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本文(ASTM D5144-2008e1 Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants《核发电厂保护涂料标准使用的标准指南》.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 D5144-2008e1 Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants《核发电厂保护涂料标准使用的标准指南》.pdf

1、Designation: D 5144 081Standard Guide forUse of Protective Coating Standards in Nuclear PowerPlants1This standard is issued under the fixed designation D 5144; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of last revisi

2、on. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon () indicates an editorial change since the last revision or reapproval.1NOTEThe title of Guide D5163was corrected editorially in April 2009.INTRODUCTIONProtective coatings (paints) have been used extensively in t

3、he nuclear industry to protect thesurfaces of facilities 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 whic

4、h were useful in theirparticular operation. Understandably, 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

5、 systematically preparespecimens and subject them to selected 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

6、 subsequent events which might lead to the release or 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 biologic

7、al environment during and after this improbable event. 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 coati

8、ngs. If severedelamination, peeling, or flaking causes 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. S

9、afety-relatedcoatings may also exist outside of the reactor-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 40 years. Standardspertaining to nuclear coatings have

10、historically been covered by ANSI N5.12, ANSI N101.2, 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 obje

11、ctive of this guide is to provide a common basis on which 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 assuran

12、ce in the nuclear industry is a mandatory requirement 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 1

13、0CFR50.65 must satisfy the requirements of 10CFR50.65. ASMESection XI, Subsection IWE contains the requirements for periodic evaluation of the reactor-containment steel pressure boundary.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United State

14、s.1. Scope1.1 This guide provides a common basis on which 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 en

15、viron-mental operating and accident conditions of nuclear 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;con

16、tamination by radioactive nuclides and subsequent decon-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

17、 Conductivity 5Surface Preparation, Coating Application, 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

18、 field) and coating application, (shop and field).1.2.2 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 measure

19、ment are included in thisstandard.1.4 This standard does 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 limita

20、tions prior to use.2. Referenced Documents2.1 ASTM Standards:3C 177 Test Method for Steady-State Heat Flux Measure-ments and Thermal Transmission Properties by Means ofthe Guarded-Hot-Plate ApparatusD 3843 Practice for Quality Assurance for Protective Coat-ings Applied to Nuclear FacilitiesD 3911 Te

21、st Method for Evaluating Coatings Used in Light-Water Nuclear Power Plants at Simulated Design BasisAccident (DBA) ConditionsD 3912 Test Method for Chemical Resistance of CoatingsUsed in Light-Water Nuclear Power PlantsD 4060 Test Method for Abrasion Resistance of OrganicCoatings by the Taber Abrase

22、rD 4082 Test Method for Effects of Gamma Radiation onCoatings for Use in Light-Water Nuclear Power PlantsD 4227 Practice for Qualification of CoatingApplicators forApplication of Coatings to Concrete SurfacesD 4228 Practice for Qualification of CoatingApplicators forApplication of Coatings to Steel

23、SurfacesD 4537 Guide for Establishing Procedures to Qualify andCertify Personnel Performing Coating Work Inspection inNuclear FacilitiesD 4538 Terminology Relating to Protective Coating andLining Work for Power Generation FacilitiesD 4541 Test Method for Pull-Off Strength of CoatingsUsing Portable A

24、dhesion TestersD 5139 Specification for Sample Preparation for Qualifica-tion Testing of Coatings to be Used in Nuclear PowerPlantsD 5163 Guide for Establishing a Program for ConditionAssessment of Coating Service Level I Coating Systems inNuclear Power PlantsD 7167 Guide for Establishing Procedures

25、 to Monitor thePerformance of Safety-Related Coating Service Level IIILining Systems in an Operating Nuclear Power PlantD 7230 Guide for Evaluating Polymeric Lining Systems forWater Immersion in Coating Service Level III Safety-Related Applications on Metal SubstratesD 7234 Test Method for Pull-Off

26、Adhesion Strength ofCoatings on Concrete Using Portable Pull-Off AdhesionTestersD 7491 Guide for Management of Non-Conforming Coat-ings in Coating Service Level I Areas of Nuclear PowerPlantsE84 Test Method for Surface Burning Characteristics ofBuilding MaterialsE 684 Practice for Approximate Determ

27、ination of CurrentDensity of Large-Diameter Ion Beams for Sputter DepthProfiling of Solid SurfacesE 1461 Test Method for Thermal Diffusivity by the FlashMethodE 1530 Test Method for Evaluating the Resistance to Ther-mal Transmission of Materials by the Guarded Heat FlowMeter Technique2.2 Other Stand

28、ards:ANSI N5.12 Protective Coatings (Paints) for the NuclearIndustry4ANSI N101.2 Protective Coatings (Paints) for Light WaterNuclear Reactor Containment Facilities4ANSI N101.4 Quality Assurance for Protective CoatingsApplied to Nuclear Facilities41This guide is under the jurisdiction of ASTM Committ

29、ee D33 on ProtectiveCoating and Lining Work for Power Generation Facilities and is the directresponsibility of Subcommittee D33.02 on Service and Material Parameters.Current edition approved Nov. 15, 2008. Published January 2009. Originallyapproved in 1991. Last previous edition approved in 2000 as

30、D 5144 00.2CertainASTM standards are available in compilation form (which includes 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

31、, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.4Available from American National Standards Institute (ANSI), 25 W. 43rd St.,4th Floor, New

32、 York, NY 10036, http:/www.ansi.org.D51440812ASME Boiler and Pressure Vessel Code (BPVC) SectionXI, Rules for Inservice Inspection of Nuclear Power PlantComponents, Subsection IWE Requirements for ClassMC and Metallic Liners of Class CC Components ofLight-Water Cooled Power Plants5EPRI 1003102 (Nove

33、mber 2001) Guideline on NuclearSafety-Related Coatings Revision 1 (formerly TR-109937)610CFR50 Appendix B: Title 10, Chapter 1, Energy, Part 50,Domestic Licensing of Production and Utilization Facili-ties, Appendix B, Quality Assurance Criteria for NuclearPower Plants and Fuel Reprocessing Plants710

34、CFR50.65 Requirements for Monitoring the Effective-ness of Maintenance at Nuclear Power Plants7Guide 1.54 Regulatory/(1973) Quality Assurance Require-ments for Protective Coatings Applied to Water-CooledNuclear Power Plants7USNRC Standard Review Plan 6.1.2 Protective CoatingSystems (Paints) Organic

35、Materials7USNRC Regulatory Guide 8.8 Information Relevant toEnsuring that Occupational Radiation Exposures AtNuclear Power Stations Will BeAs LowAs Is ReasonablyAchievable73. Terminology3.1 DefinitionsDefinitions for use with this guide areshown in Terminology D 4538 or other applicable standards.4.

36、 Significance and Use4.1 This guide addresses the concerns of Regulation 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

37、coating workin Coating Service Level I and III areas (that is, 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

38、is particularlyappropriate for safety-related coatings inside the 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

39、coatings shall beaddressed in job specifications. Guidance for selecting andperformance monitoring of Coating Service Level III coatingsis provided Guides D 7230 and D 7167 respectively, andSections 4.4 and 4.5 of EPRI 1003102 (formerly TR-109937).4.3 Users of this guide must ensure that coatings wo

40、rkcomplies not only with this guide, but also with 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 pr

41、ovides the minimum requirementsfor qualifying Coating 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 C

42、oating Service Level I Coatings:4.4.2.1 All Coating 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 D 3911 or plant sp

43、ecific requirements asapplicable,(b) Test Method D 4082, and(c) Specification D 5139.4.4.2.2 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 lic

44、ensing commitments.The following documents provide guidance for application,possible additional testing or for the further evaluation ofCoating Service Level I coatings when applicable:(a) Test Method C 177,(b) Practice D 3843,(c) Test Method D 3912,(d) Test Method D 4060,(e) Practice D 4227,(f) Pra

45、ctice D 4228,(g) Guide D 4537,(h) Test Method D 4541,(i) Test Method E84,(j) Test Method E 1461, and(k) Test Method E 1530.4.4.2.3 Condition assessment and management of CoatingService Level I coatings is also required by the licensee tomaintain the coatings following the initial application andsubs

46、equent repairs. The following documents provide guidancefor the monitoring and management of the Coating ServiceLevel I coatings:(a) Guide D 5163 and(b) Guide D 7491.4.4.3 Coating Service Level III Coatings:4.4.3.1 Coating Service Level III coatings must be evalu-ated for use in accordance with the

47、requirements of plantlicensing commitments and 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 qualificati

48、on requirementsincluded in this guide for Coating Service Level III coatings orlinings. Testing and evaluation of Coating Service Level III5Available from American Society of Mechanical Engineers (ASME), ASMEInternational Headquarters, Three Park Ave., New York, NY 10016-5990, http:/www.asme.org.6Av

49、ailable from EPRI Distribution Center, 207 Coggins Drive, P.O. Box 23205,Pleasant Hills, CA 94523 (510) 934-4212.7Available from U.S. Government Printing Office Superintendent of Documents,732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http:/www.access.gpo.gov.D51440813coatings should be conducted as necessary to ensure that thecoatings are suitable for the specific service environment. Thefollowing documents provide guidance for testing and inspec-tion, which the licensee may consider when preparing jobspecifications for Coating Service Level III coatings o

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