1、Designation:C146200(Reapproved 2013)Standard Specification forUranium Metal Enriched to More than 15%and Less Than20%235U1This standard is issued under the fixed designation C1462;the number immediately following the designation indicates the year oforiginal adoption or,in the case of revision,the y
2、ear 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 nuclear grade uranium metalthat has either been processed through an enrichment plant,orha
3、s been produced by the blending of highly enriched uraniumwith other uranium,to obtain uranium of any235U concentra-tion below 20%(and greater than 15%)and that is intendedfor research reactor fuel fabrication.The scope of this speci-fication includes specifications for enriched uranium metalderived
4、 from commercial natural uranium,recovered uranium,or highly enriched uranium.Commercial natural uranium,recovered uranium and highly enriched uranium are defined inSection 3.The objectives of this specification are to define theimpurity and uranium isotope limits for commercial gradeenriched uraniu
5、m metal.1.2 This specification is intended to provide the nuclearindustry with a standard for enriched uranium metal which is tobe used in the production of research reactor fuel.In additionto this specification,the parties concerned may agree to otherappropriate conditions.1.3 The scope of this spe
6、cification does not comprehen-sively cover all provisions for preventing criticality accidentsor requirements for health and safety or for shipping.Obser-vance of this standard does not relieve the user of theobligation to conform to all applicable international,federal,state,and local regulations f
7、or processing,shipping,or anyother way of using uranium metal(see,for example,C996regarding references).2.Referenced Documents2.1 ASTM Standards:2C696 Test Methods for Chemical,Mass Spectrometric,andSpectrochemical Analysis of Nuclear-Grade Uranium Di-oxide Powders and PelletsC799 Test Methods for C
8、hemical,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 Boron Contentsof Nuclea
9、r MaterialsC1295 Test Method for Gamma Energy Emission fromFission Products in Uranium Hexafluoride and UranylNitrate SolutionC1347 Practice for Preparation and Dissolution of UraniumMaterials for Analysis2.2 ANSI Standard3ANSI-ASME NQA-1 Quality Assurance Program Require-ments for Nuclear Facility
10、Applications2.3 U.S.Government Documents4Code of Federal Regulations,Title 10,Part 50,(Appendix B)3.Terminology3.1 Definitions of Terms Specific to This Standard:3.1.1 Definitions of Terms Specific to This StandardTerms shall be defined in accordance with Terminology C859,except for the following:3.
11、1.2 commercial grade enriched uranium metaluraniummetal derived from commercial natural uranium,recovereduranium,or uranium obtained from the blending of highlyenriched uranium with commercial natural uranium,recovereduranium,or depleted uranium.3.1.3 commercial natural uraniumany form of naturaluni
12、rradiated uranium(containing 0.711+0.004 g235U per 100g U).3.1.4 depleted uraniumany form of unirradiated uraniumwith a235U content less than commercial natural uranium.1This specification is under the jurisdiction of ASTM Committee C26 onNuclear Fuel Cycle and is the direct responsibility of Subcom
13、mittee C26.02 on Fueland Fertile Material Specifications.Current edition approved Jan.1,2013.Published January 2013.Originallyapproved in 2000.Last previous edition approved in 2008 as C1462 00(2008).DOI:10.1520/C1462-00R13.2For referenced ASTM standards,visit the ASTM website,www.astm.org,orcontact
14、 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 National Standards Institute(ANSI),25 W.43rd St.,4th Floor,New York,NY 10036,http:/www.ansi.org.4Available from U.S.G
15、overnment Printing Office Superintendent of Documents,732 N.Capitol St.,NW,Mail Stop:SDE,Washington,DC 20401,http:/www.access.gpo.gov.Copyright ASTM International,100 Barr Harbor Drive,PO Box C700,West Conshohocken,PA 19428-2959.United States1 3.1.5 highly enriched uraniumany form of uranium hav-ing
16、 a235U content equal to or in excess of 20%.3.1.6 recovered uraniumany form of uranium that hasbeen exposed in a neutron irradiation facility and either hasbeen subsequently chemically separated from the fission prod-ucts and transuranic isotopes so generated,or may be used asis,due to low irradiation levels.3.1.6.1 DiscussionThe requirements for recovered ura-nium are intended to be typical of reprocessed spent fuel fromresearch reactors that have achieved burn-up levels of up to50%of the origi