ASTM E2215-2018 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels.pdf
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1、Designation: E2215 18Standard Practice forEvaluation of Surveillance Capsules from Light-WaterModerated Nuclear Power Reactor Vessels1This standard is issued under the fixed designation E2215; the number immediately following the designation indicates the year oforiginal adoption or, in the case of
2、revision, the year 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.1. Scope1.1 This practice covers the evaluation of test specimensand dosimetry from light water moderated nu
3、clear powerreactor pressure vessel surveillance capsules.1.2 Additionally, this practice provides guidance on reas-sessing withdrawal schedule for design life and operationbeyond design life.1.3 This practice is one of a series of standard practices thatoutline the surveillance program required for
4、nuclear reactorpressure vessels. The surveillance program monitors theirradiation-induced changes in the ferritic steels that comprisethe beltline of a light-water moderated nuclear reactor pressurevessel.1.4 This practice along with its companion surveillanceprogram practice, Practice E185, is inte
5、nded for application inmonitoring the properties of beltline materials in any light-water moderated nuclear reactor.21.5 Modifications to the standard test program and supple-mental tests are described in Guide E636.1.6 The values stated in SI units are to be regarded as thestandard. The values give
6、n in parentheses are for informationonly.1.7 This international standard was developed in accor-dance with internationally recognized principles on standard-ization established in the Decision on Principles for theDevelopment of International Standards, Guides and Recom-mendations issued by the Worl
7、d Trade Organization TechnicalBarriers to Trade (TBT) Committee.2. Referenced Documents2.1 ASTM Standards:3A370 Test Methods and Definitions for Mechanical Testingof Steel ProductsE8/E8M Test Methods for Tension Testing of Metallic Ma-terialsE21 Test Methods for Elevated Temperature Tension Tests of
8、Metallic MaterialsE23 Test Methods for Notched Bar Impact Testing of Me-tallic MaterialsE170 Terminology Relating to Radiation Measurements andDosimetryE185 Practice for Design of Surveillance Programs forLight-Water Moderated Nuclear Power Reactor VesselsE208 Test Method for Conducting Drop-Weight
9、Test toDetermine Nil-Ductility Transition Temperature of Fer-ritic SteelsE509 Guide for In-Service Annealing of Light-Water Mod-erated Nuclear Reactor VesselsE636 Guide for Conducting Supplemental SurveillanceTests for Nuclear Power Reactor VesselsE693 Practice for Characterizing Neutron Exposures i
10、n Ironand Low Alloy Steels in Terms of Displacements PerAtom (DPA)E844 Guide for Sensor Set Design and Irradiation forReactor SurveillanceE853 Practice forAnalysis and Interpretation of Light-WaterReactor Surveillance ResultsE900 Guide for Predicting Radiation-Induced TransitionTemperature Shift in
11、Reactor Vessel MaterialsE1214 Guide for Use of Melt Wire Temperature Monitorsfor Reactor Vessel SurveillanceE1253 Guide for Reconstitution of Irradiated Charpy-SizedSpecimensE1820 Test Method for Measurement of Fracture Toughness1This practice is under the jurisdiction of ASTM Committee E10 on Nucle
12、arTechnology and Applications and is the direct responsibility of SubcommitteeE10.02 on Behavior and Use of Nuclear Structural Materials.Current edition approved Aug. 1, 2018. Published August 2018. Originallyapproved in 2002. Last previous edition approved in 2016 as E221516. DOI:10.1520/E2215-18.2
13、Prior to the adoption of these standard practices, surveillance capsule testingrequirements were only contained in Practice E185.3For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume informati
14、on, refer to the standards Document Summary page onthe ASTM website.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United StatesThis international standard was developed in accordance with internationally recognized principles on standardization e
15、stablished in the Decision on Principles for theDevelopment of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.1E1921 Test Method for Determination of ReferenceTemperature, To, for Ferritic Steels in the Transitio
16、nRange2.2 ASME Standards:4Boiler and Pressure Vessel Code, Section III SubarticleNB-2000, Rules for Construction of Nuclear FacilityComponents, Class 1 Components, MaterialsBoiler and Pressure Vessel Code, Section XI NonmandatoryAppendix A, Analysis of Flaws, and Nonmandatory Ap-pendix G, Fracture T
17、oughness Criteria for Protectionagainst Failure3. Terminology3.1 Definitions:3.1.1 base metalas-fabricated plate material or forgingmaterial other than a weld or its corresponding heat-affected-zone (HAZ).3.1.2 beltlinethe irradiated region of the reactor vessel(shell material including weld seams a
18、nd plates or forgings)that directly surrounds the effective height of the active core.Note that materials in regions adjacent to the beltline maysustain sufficient neutron damage to warrant consideration inthe selection of surveillance materials.3.1.3 Charpy transition temperature curvea graphic orc
19、urve-fitted presentation, or both, of absorbed energy, lateralexpansion, or fracture appearance as a function of testtemperature, extending over a range including the lower shelf(5 % or less shear fracture appearance), transition region, andthe upper shelf (95 % or greater shear fracture appearance)
20、.3.1.4 Charpy transition temperature shiftthe difference inthe 41 J (30 ft-lbf) index temperatures for the best fit (average)Charpy absorbed energy curve measured before and afterirradiation. Similar measures of temperature shift can bedefined based on other indices in 3.1.3, but the current U.S.ind
21、ustry practice is to use 41 J (30 ft-lbf) and is consistent withGuide E900.3.1.5 Charpy upper-shelf energy levelthe average energyvalue for all Charpy specimen tests (preferably three or more)whose test temperature is at or above the Charpy upper-shelfonset; specimens tested at temperatures greater
22、than 83C(150F) above the Charpy upper-shelf onset shall not beincluded, unless no data are available between the onsettemperature and onset +83C (+150F).3.1.6 Charpy upper-shelf onsetthe temperature at whichthe fracture appearance of all Charpy specimens tested is at orabove 95 % shear.3.1.7 end-of-
23、license (EOL) fluencethe maximum pre-dicted fluence at the inside surface of the ferritic pressurevessel (if clad, the interface between cladding and ferritic steel)corresponding to the end of the applicable operating licenseperiod.3.1.8 heat-affected-zone (HAZ)plate material or forgingmaterial exte
24、nding outward from, but not including, the weldfusion line in which the microstructure of the base metal hasbeen altered by the heat of the welding process.3.1.9 index temperaturethe temperature corresponding toa predetermined level of absorbed energy, lateral expansion, orfracture appearance obtain
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