ASTM_C_753_-_16a.pdf

Designation:C75316aStandard Specification forNuclear-Grade,Sinterable Uranium Dioxide Powder1This standard is issued under the fixed designation C753;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.INTRODUCTIONThis specification is intended to provide the nuclear industry with a general standard for sinterableuranium dioxide(UO2)powder.It recognizes the diversity of manufacturing methods by which UO2powders are produced and the many special requirements for chemical and physical characterizationthat may be applicable for a particular fuel pellet manufacturing process or imposed by the end userof the powder in a specific reactor system.It is,therefore,anticipated that the buyer may supplementthis specification with more stringent or additional requirements for specific applications.1.Scope1.1 This specification covers nuclear-grade,sinterable UO2powder.It applies to UO2powder containing uranium(U)ofany235U concentration in the production of nuclear fuel pelletsfor use in nuclear reactors.1.2 This specification recognizes the presence of repro-cessed U in the fuel cycle and consequently defines isotopiclimits for commercial grade UO2.Such commercial grade UO2is defined so that,regarding fuel design and manufacture,theproduct is essentially equivalent to that made from unrepro-cessed U.UO2falling outside these limits cannot necessarilybe regarded as equivalent and may thus need special provisionsat the fuel fabrication plant or in the fuel design.1.3 This specification does not include provisions for pre-venting criticality accidents or requirements for health andsafety.Observance of this specification does not relieve theuser of the obligation to be aware of and conform to allinternational,national,or federal,state,and local regulationspertaining to possessing,shipping,processing,or using sourceor special nuclear material.1.4 This specification refers expressly to UO2powder be-fore the addition of any die lubricant,binder,or pore former.Ifpowder is sold with such additions or prepared as press feed,sampling procedures,allowable impurity contents,or powderphysical requirements may need to be modified by agreementbetween the buyer and the seller.1.5 The values stated in SI units are to be regarded as thestandard.The values given in parentheses are for informationonly.1.6 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 requirements prior to use.2.Referenced Documents2.1 ASTM Standards:2B243 Terminology of Powder MetallurgyB329 Test Method for Apparent Density of Metal Powdersand Compounds Using the Scott VolumeterC696 Test Methods for Chemical,Mass Spectrometric,andSpectrochemical Analysis of Nuclear-Grade Uranium Di-oxide Powders and PelletsC859 Terminology Relating to Nuclear MaterialsC996 Specification for Uranium Hexafluoride Enriched toLess Than 5%235UC1233 Practice for Determining Equivalent Boron Contentsof Nuclear MaterialsE11 Specification for Woven Wire Test Sieve Cloth and TestSievesE105 Practice for Probability Sampling of Materials2.2 ASME Standard:3ASME NQA-1 QualityAssurance Requirements for NuclearFacility Applications1This specification is under the jurisdiction of ASTM Committee C26 onNuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fueland Fertile Material Specifications.Current edition approved April 1,2016.Published April 2016.Originallyapproved in 1973.Last previous edition approved in 2016 as C753 16.DOI:10.1520/C0753-16A.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.Copyright ASTM International,100 Barr Harbor Drive,PO Box C700,West Conshohocken,PA 19428-2959.United States1 2.3 Federal Regulation:4Code of Federal Regulations,Title 10,Chapter 1,NuclearRegulatory Commission,Applicable Parts3.Terminology3.1 DefinitionsDefinitions of terms are as given in Termi-nologies B243 and C859.4.Chemical Composition4.1 Uranium ContentThe U content shall be determinedon a basis to be agreed upon between the buyer and seller.4.2 Oxygen-to-Uranium Ratio(O/U)The O/U ratio maybe specified as agreed upon between the buyer and seller.Thedetermination of the O/U ratio shall be in accordance with TestMethods C696 or a demonstrated equivalent.4.3 Impurity ContentThe impurity content shall not ex-ceed the indivi