ANSI ASTM D7301-2011 Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose《适用于受低中子Irr Adiation剂量影响元件的核石墨用规范》.pdf
《ANSI ASTM D7301-2011 Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose《适用于受低中子Irr Adiation剂量影响元件的核石墨用规范》.pdf》由会员分享,可在线阅读,更多相关《ANSI ASTM D7301-2011 Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose《适用于受低中子Irr Adiation剂量影响元件的核石墨用规范》.pdf(5页珍藏版)》请在麦多课文档分享上搜索。
1、Designation: D7301 11 (Reapproved 2015) An American National StandardStandard Specification forNuclear Graphite Suitable for Components Subjected toLow Neutron Irradiation Dose1This standard is issued under the fixed designation D7301; the number immediately following the designation indicates the y
2、ear oforiginal adoption or, in the case of 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 specification covers the classification, process
3、ing,and properties of nuclear grade graphite billets with dimen-sions sufficient to meet the designers requirements for reflec-tor blocks and core support structures, in a high temperaturegas cooled reactor. The graphite classes specified here wouldbe suitable for reactor core applications where neu
4、tron irradia-tion induced dimensional changes are not a significant designconsideration.1.2 The purpose of this specification is to document theminimum acceptable properties and levels of quality assuranceand traceability for nuclear grade graphite suitable for compo-nents subjected to low irradiati
5、on dose. Nuclear graphitesmeeting the requirements of Specification D7219 are alsosuitable for components subjected to low neutron irradiationdose.1.3 The values stated in SI units are to be regarded asstandard. No other units of measurement are included in thisstandard.2. Referenced Documents2.1 AS
6、TM Standards:2C559 Test Method for Bulk Density by Physical Measure-ments of Manufactured Carbon and Graphite ArticlesC709 Terminology Relating to Manufactured Carbon andGraphiteC781 Practice for Testing Graphite and Boronated GraphiteMaterials for High-Temperature Gas-Cooled Nuclear Re-actor Compon
7、entsC838 Test Method for Bulk Density of As-ManufacturedCarbon and Graphite ShapesC1233 Practice for Determining Equivalent Boron Contentsof Nuclear MaterialsD346 Practice for Collection and Preparation of CokeSamples for Laboratory AnalysisD2638 Test Method for Real Density of Calcined PetroleumCok
8、e by Helium PycnometerD7219 Specification for Isotropic and Near-isotropicNuclear GraphitesIEEE/ASTM SI 10 American National Standard for Use ofthe International System of Units (SI): The Modern MetricSystem2.2 ASME Standards:3NQA-1 Quality Assurance Program Requirements forNuclear Facilities3. Term
9、inology3.1 DefinitionsDefinitions relating to this specification aregiven in Terminology C709. See Table 1.3.2 Definitions of Terms Specific to This Standard:3.2.1 anistropic nuclear graphite, ngraphite in which theisotropy ratio based on the coefficient of thermal expansion isgreater than 1.15.3.2.
10、2 baking/re-baking charge, nnumber of billets in abaking/re-baking furnace run.3.2.3 bulk density, nmass of a unit volume of materialincluding both permeable and impermeable voids.3.2.4 extrusion forming lot, nnumber of billets of thesame size extruded in an uninterrupted sequence.3.2.5 green batch,
11、 nmass of coke, recycle green mix,recycle graphite, and pitch that is required to produce aforming lot.3.2.6 green mix, npercentage of mix formulation, pitchand additives required for the forming lot, which is processedand ready to be formed.3.2.7 graphite billet, nextruded, molded, or iso-moldedgra
12、phite artifact with dimensions sufficient to meet the design-ers requirements for reactor components.1This specification is under the jurisdiction of ASTM Committee D02 onPetroleum Products, Liquid Fuels, and Lubricants and is the direct responsibility ofSubcommittee D02.F0 on Manufactured Carbon an
13、d Graphite Products.Current edition approved June 1, 2015. Published July 2015. Originally approvedin 2008. Last previous edition approved in 2011 as D7301 11. DOI: 10.1520/D7301-11R15.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceast
14、m.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.3Available from American Society of Mechanical Engineers (ASME), ASMEInternational Headquarters, Three Park Ave., New York, NY 10016-5990, http:/www.asme.org.Copyright ASTM Int
15、ernational, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States13.2.8 graphite grade, ndesignation given to a material bya manufacturer such that it is always reproduced to the samespecification and from the same raw materials and mixformulation.3.2.9 graphitizing fur
16、nace run, ntotal number of billetsgraphitized together in one graphitization furnace.3.2.10 graphitization charge, ntotal number of billetsgraphitized together in one graphitization furnace.3.2.11 high purity nuclear graphite, nnuclear graphitewith an Equivalent Boron Content less than 2 ppm.3.2.12
17、impregnation charge, nnumber of billets in anautoclave cycle.3.2.13 low purity nuclear graphite, nnuclear graphite withan Equivalent Boron Content greater than 2 ppm but less than10 ppm.3.2.14 mix formulation, npercentages of each specificallysized filler used to manufacture a graphite grade.3.2.15
18、molding forming lot, nnumber of billets moldedfrom a molding powder lot.3.2.16 molding powder lot, nsufficient quantity of re-milled and blended green batch produced from an uninter-rupted flow of raw materials, or produced in a sequence ofidentical materials batches, to produce a molding forming lo
19、t.3.2.17 nuclear graphite class, ndesignation of a nucleargraphite based upon its forming method, isotropy, purity anddensity (see Table 2).3.2.18 production lot, nspecified number of billets madein accordance with this specification and additional require-ments determined by the purchaser.3.2.19 pu
20、rification charge, nnumber of billets in a purifi-cation run.3.2.20 recycle green mix, nground non-baked billets ornon-used green mix manufactured in compliance with the mixformulation specified here.4. Materials and Manufacture4.1 Nuclear Graphite ClassesSee Table 2.4.2 Raw Materials:4.2.1 Fillers:
21、4.2.1.1 The filler shall consist of a coke derived from apetroleum oil or coal tar.4.2.1.2 The coke shall have a coefficient of linear thermalexpansion (CTE), determined in accordance with PracticeC781 and measured over the temperature range 25 C to500 C, less than 5.5 10-6C-1.4.2.1.3 The coke shall
22、 be sampled and distributed as de-scribed in Table 3.4.2.1.4 Graphite manufactured in compliance with thisspecification but failing to meet the property requirements ofSections 57may be used as recycle material in the mixformulation.4.2.1.5 Recycle green mix manufactured from raw materialsin complia
23、nce with this specification may be used in the mixformulation.4.2.1.6 The maximum filler particle size used in the mixformulation shall be 1.68 mm.4.3 BinderThe binder shall consist of coal tar pitch of thesame grade from the same manufacturer. The specific binder(s)used shall be identified to the p
24、urchaser and be traceablethrough the forming lot.4.4 ImpregnantThe impregnant shall consist of a petro-leum or coal tar pitch of the same grade from the samemanufacturer. The specific impregnant(s) used shall be identi-fied to the purchaser and be traceable through the impregnationsteps.4.5 Manufact
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