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
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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
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