ASTM_D_7301_-_21.pdf

Designation:D730121Standard 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 year 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.Scope*1.1 This specification covers the classification,processing,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 neutron 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 irradiation 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.1.4 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 World Trade Organization TechnicalBarriers to Trade(TBT)Committee.2.Referenced Documents2.1 ASTM Standards:2C561 Test Method for Ash in a Graphite SampleC781 Practice for Testing Graphite Materials for Gas-CooledNuclear Reactor ComponentsC838 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 PetroleumCoke by Helium PycnometerD4175 Terminology Relating to Petroleum Products,LiquidFuels,and LubricantsD7219 Specification for Isotropic and Near-isotropicNuclear GraphitesD8186 Test Method for Measurement of Impurities inGraphite by Electrothermal Vaporization InductivelyCoupled Plasma Optical Emission Spectrometry(ETV-ICP OES)IEEE/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.Terminology3.1 DefinitionsDefinitions relating to this specification aregiven in Terminology D4175.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 1.15.3.2.2 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.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 and Graphite Products.Current edition approved Nov.1,2021.Published November 2021.Originallyapproved in 2008.Last previous edition approved in 2015 as D7301 11(2015).DOI:10.1520/D7301-21.2For referenced ASTM standards,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.3Available from American Society of Mechanical Engineers(ASME),ASMEInternational Headquarters,Two Park Ave.,New York,NY 10016-5990,http:/www.asme.org.*A Summary of Changes section appears at the end of this standardCopyright 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 established 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.1?3.2.5 green batch,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-moldedgraphite artifact with dimensions sufficient to meet the design-ers requirements for reactor components.3.2.8 graphite grade,ndesignat