1、Designation:C96713Standard Specification forUranium Ore Concentrate1This standard is issued under the fixed designation C967;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
2、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 uraniumore concentrate.Material conforming to this specification will generally
3、 meet the requirements forconversion to uranium hexafluoride.However,the converter may relax or supplement this specifica-tion upon mutual agreement with the customer.1.Scope1.1 This specification covers uranium ore concentrate con-taining a minimum of 65 mass%uranium.1.2 This specification does not
4、 include requirements forhealth and safety.Observance of this specification does notrelieve the user of the obligation to be aware of and conform toall applicable international,national,state,and local regula-tions pertaining to possessing,shipping,or using sourcenuclear material(see 2.2).1.3 The va
5、lues stated in SI units are to be regarded as thestandard.The values given in parentheses are for informationonly.2.Referenced Documents2.1 ASTM Standards:2C859 Terminology Relating to Nuclear MaterialsC1022 Test Methods for Chemical and Atomic AbsorptionAnalysis of Uranium-Ore ConcentrateC1075 Prac
6、tices for Sampling Uranium-Ore ConcentrateC1380 Test Method for the Determination of Uranium Con-tent and Isotopic Composition by Isotope Dilution MassSpectrometry2.2 U.S.Government Documents:Nuclear Materials Licensing Code of Federal Regulations,Energy Title 10,Chapter 1,Nuclear Regulatory Commis-
7、sion3Nuclear Materials Licensing Code of Federal Regulations,Title 49,Transportation Chapter 1,Materials Transporta-tion Bureau4Nuclear Materials Licensing Code of Federal Regulations,Energy Part 50(10CFR 50)Licensing of Domestic Pro-duction and Utilization Facilities32.3 ANSI Standard:5ANSI/ASME NQ
8、A-1 Quality Assurance Requirements forNuclear Facility Applications3.Definitions3.1 Except as otherwise defined herein,definitions of termsare as given in Terminology C859.4.Chemical Composition4.1 Uranium ContentThe uranium content,as received,shall be a minimum of 65 mass%.4.2 Isotopic ContentThe
9、isotopic content shall be that ofnaturally occurring uranium(0.711 6 0.001 g235U per 100 g(see Note 1).The234U content shall not exceed the limits inTable 1.1This specification is under the jurisdiction of ASTM Committee C26 onNuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.0
10、2 on Fueland Fertile Material Specifications.Current edition approved Jan.1,2013.Published January 2013.Originallyapproved in 1981.Last previous edition approved in 2012 as C967 12.DOI:10.1520/C0967-13.2For referenced ASTM standards,visit the ASTM website,www.astm.org,orcontact ASTM Customer Service
11、 at serviceastm.org.For Annual Book of ASTMStandards volume information,refer to the standards Document Summary page onthe ASTM website.3Available from the Nuclear Regulatory Commission,Washington,DC,20555-0001,www.nrc.gov.4Available from the Materials Transportation Bureau,400 Seventh St.,Washingto
12、n,DC,20590.5Available from American National Standards Institute(ANSI),25 W.43rd St.,4th Floor,New York,NY 10036,http:/www.ansi.org.Copyright ASTM International,100 Barr Harbor Drive,PO Box C700,West Conshohocken,PA 19428-2959.United States1 NOTE1For ore concentrate from verifiable source(for exampl
13、e,through the sellers quality assurance records),the235U analysis is notnormally required unless otherwise agreed upon between the buyer andseller.4.3 Insoluble UraniumThe uranium insoluble in nitricacid shall be a maximum of 0.10 mass%on a uranium basis.4.4 Extractable OrganicDepending on the conve
14、rsionprocess(dry route vs.wet route),the need for measurement ofextractable organic shall be agreed upon between buyer andseller(see Note 2).NOTE2If a measurement is requested,a limit of 0.1 g per 100 g of oreconcentrate shall be used.4.5 Impurity ContentThe impurity content shall be lessthan the ma
15、ximum limits specified in Table 1.4.6 Uranium DaughtersLong-lived radionuclides,such as231Pa,230Th,and226Ra,may concentrate in residues andtherefore may impact storage and transportation of wastes.Conversion facilities should be aware that their level can vary.Determination of these elements and the
16、 analytical frequencymay be agreed between buyer and seller.5.Physical Properties5.1 Particle SizeAll of a representative sample(Section 6)shall pass through a sieve with an aperature of14in.5.2 Ability to FlowConcentrate shall be sufficiently free-flowing to permit sampling.5.3 Foreign MatterConcentrate shall be free of all mate-rials and objects that:(a)are not produced as a constituent ofconcentrates in the milling of uranium ore,or,(b)would orcould be detrimental to the sampling of concentra
