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
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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
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