1、Designation:C134801(Reapproved 2008)Standard Specification forBlended Uranium Oxides with235U Content of Less Than5%for Direct Hydrogen Reduction to Nuclear GradeUranium Dioxide1This standard is issued under the fixed designation C1348;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.INTRODUCTIONThis specification is intended to provide the nuclear indus
3、try with a general standard for suchuranium oxide powders.It recognizes the diversity of conversion processes and the many specialrequirements for chemical and physical characterization that may be imposed by the end use of thepowder.It is anticipated,therefore,that this specification may be supplem
4、ented with additionalrequirements by agreement between the buyer and the seller.1.Scope1.1 This specification covers blended uranium trioxide(UO3),U3O8,or mixtures of the two,powders that are intendedfor conversion into a sinterable uranium dioxide(UO2)powderby means of a direct reduction process.Th
5、e UO2powderproduct of the reduction process must meet the requirements ofSpecification C753 and be suitable for subsequent UO2pelletfabrication by pressing and sintering methods.This specifica-tion applies to uranium oxides with a235U enrichment less than5%.1.2 This specification includes chemical,p
6、hysical,and testmethod requirements for uranium oxide powders as they relateto the suitability of the powder for storage,transportation,anddirect reduction to UO2powder.This specification is applicableto uranium oxide powders for such use from any source.1.3 The scope of this specification does not
7、comprehen-sively cover all provisions for preventing criticality accidents,for health and safety,or for shipping.Observance of thisspecification does not relieve the user of the obligation toconform to all international,national,state,and local regula-tions for processing,shipping,or any other way o
8、f usinguranium oxide powders(see 2.2 and 2.3).1.4 The values stated in SI units are to be regarded as thestandard.The values given in parentheses are for informationonly.1.5 The following safety hazards caveat pertains only to thetest methods portion of the annexes in this specification:Thisstandard
9、 does not purport to address all of the safety concerns,if any,associated with its use.It is the responsibility of the userof this standard to establish appropriate safety and healthpractices and determine the applicability of regulatory limita-tions prior to use.2.Referenced Documents2.1 ASTM Stand
10、ards:2B329 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 PelletsC753 Specification for Nuclear-Grade,Sinterable UraniumDioxide PowderC
11、799 Test Methods for Chemical,Mass Spectrometric,Spectrochemical,Nuclear,and Radiochemical Analysis ofNuclear-Grade Uranyl Nitrate SolutionsC859 Terminology Relating to Nuclear MaterialsC996 Specification for Uranium Hexafluoride Enriched toLess Than 5%235UC1233 Practice for Determining Equivalent B
12、oron Contentsof Nuclear MaterialsC1287 Test Method for Determination of Impurities inNuclear Grade Uranium Compounds by InductivelyCoupled Plasma Mass Spectrometry1This specification is under the jurisdiction of ASTM Committee C26 onNuclear Fuel Cycle and is the direct responsibility of Subcommittee
13、 C26.02 on Fueland Fertile Material Specifications.Current edition approved June 1,2008.Published August 2008.Originallyapproved in 1996.Last previous edition approved in 2001 as C1348 01.DOI:10.1520/C1348-01R08.2For referenced ASTM standards,visit the ASTM website,www.astm.org,orcontact ASTM Custom
14、er Service at serviceastm.org.For Annual Book of ASTMStandards volume information,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 StatesNOTICE:This standard has either been supersede
15、d and replaced by a new version or withdrawn.Contact ASTM International(www.astm.org)for the latest information1 E11 Specification for Woven Wire Test Sieve Cloth and TestSievesE105 Practice for Probability Sampling of Materials2.2 ANSI Standard:3NQA-1 Quality Assurance Program,Requirements forNucle
16、ar Facilities2.3 U.S.Government Document:4CFR Title 10(Energy),Part 50,Domestic Licensing ofProduction and Utilization Facilities3.Terminology3.1 DefinitionsTerms shall be defined in accordance withTerminology C859,except the following.3.2 Definitions of Terms Specific to This Standard:3.2.1 Commercial-Grade Uranium Oxideuranium triox-ide(UO3),U3O8,or a mixture of the two,made fromunirradiated uranium.It is recognized that some contaminationwith reprocessed uranium may occur during routine proce
