1、Designation: C 967 08Standard Specification forUranium Ore Concentrate1This standard is issued under the fixed designation C 967; 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 in
2、dicates the year of last reapproval. Asuperscript epsilon (e) 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 w
3、ill generally 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 spec
4、ification does not 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 mate
5、rial (see 2.2).1.3 The values stated in SI units are to be regarded as thestandard. The values given in parentheses are for informationonly.2. Referenced Documents2.1 ASTM Standards:2C 859 Terminology Relating to Nuclear Materials3C 1022 Test Methods for Chemical and Atomic AbsorptionAnalysis of Ura
6、nium-Ore ConcentrateC 1075 Practices for Sampling Uranium-Ore ConcentrateC 1380 Test Method for the Determination of UraniumContent and Isotopic Composition by Isotope DilutionMass Spectrometry2.2 U.S. Government Documents:Nuclear Materials Licensing Code of Federal RegulationsTitle 10, Chapter 1, N
7、uclear Regulatory Commission4Nuclear Materials Licensing Code of Federal Regulations,Title 49, Transportation Chapter 1, Materials Transporta-tion Bureau5Nuclear Materials Licensing Code of Federal Regulations,Energy Part 50 (10CFR 50) Licensing of Domestic Pro-duction and Utilization Facilities42.3
8、 ANSI Standard:6ANSI/ASME NQA-1 Quality Assurance Requirements forNuclear Facility Applications3. Terminology Definitions3.1 Except as otherwise defined herein, definitions of termsare as given in Terminology C 859.4. Chemical Composition4.1 Uranium ContentThe uranium content, as received,shall be a
9、 minimum of 65 mass %.4.2 Isotopic ContentThe 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.NOTE 1For ore concentrate from verifiable source (for example,through the sellers quality assur
10、ance 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 conversionprocess (dry route vs. wet
11、route), the need for measurement ofextractable organic shall be agreed upon between buyer andseller (see Note 2).NOTE 2If a measurement is requested, a limit of 0.1 g per 100 g of oreconcentrate shall be used.1This specification is under the jurisdiction of ASTM Committee C26 onNuclear Fuel Cycle an
12、d is the direct responsibility of Subcommittee C26.02 on Fueland Fertile Material Specifications.Current edition approved Jan. 1, 2008. Published January 2008. Originallyapproved in 1981. Last previous edition approved in 2002 as C 967 02a.2For referenced ASTM standards, visit the ASTM website, www.
13、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.3Withdrawn.4Available from the Nuclear Regulatory Commission, Washington, DC, 20555-0001, www.nrc.gov.5Available from the
14、 Materials Transportation Bureau, 400 Seventh St., Wash-ington, DC, 20590.6Available from American National Standards Institute (ANSI), 25 W. 43rd St.,4th Floor, New York, NY 10036, http:/www.ansi.org.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959
15、, United States.Copyright by ASTM Intl (all rights reserved); Wed Nov 5 02:32:51 EST 2008Downloaded/printed byGuo Dehua (CNIS) pursuant to License Agreement. No further reproductions authorized.4.5 Impurity ContentThe impurity content shall be lessthan the maximum limits specified in Table 1.5. Phys
16、ical Properties5.1 Particle SizeAll of a representative sample (Section6) shall pass through a sieve with an aperature of14 in.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
17、not produced as a constituent ofconcentrates in the milling of uranium ore, or, (b) would orcould be detrimental to the sampling of concentrates or to theequipment used in such sampling.6. Sampling6.1 The lot size and number of tests (and retests whenrequired) shall be as mutually agreed.6.2 A repre
18、sentative sample, of a size sufficient to performthe tests prescribed in Sections 4 and 5, shall be taken fromeach lot.6.3 Practices C 1075 is referenced as a guide.7. Test Methods7.1 All chemical analyses shall be performed on portions ofthe representative sample prepared in accordance with Section
19、6. Analytical chemistry methods shall be in accordance withTest Methods C 1022, C 1380 or as otherwise agreed.8. Certification8.1 When specified in the purchase order or contract,certification shall be furnished that the material was sampledand tested in accordance with this specification and has be
20、enfound to meet the requirements. When specified in the pur-chase order or contract, a report of the test results shall befurnished.9. Packaging and Package Marking9.1 Uranium ore concentrate shall be packaged and shippedin drums having lids fitted with watertight sealing rings. Thelids shall be att
21、ached to the drums in a manner that minimizesloss of concentrate in the event of mishandling. Shippingcontainers shall meet applicable regulatory requirements. CFRTitle 10 and Title 49 are referenced as guides.9.2 Each container shall bear, as a minimum, labels on thelid and side with the following
22、information:9.2.1 Sellers name,9.2.2 Material in containers,9.2.3 Lot number,9.2.4 Gross, tare and net weights, and9.2.5 Container ( ) of ( ).10. Quality Assurance10.1 Quality assurance requirements shall be as agreed uponbetween the buyer and the seller when specified in the purchaseorder. Code of
23、Federal Regulations Title 10, Part 50, AppendixB and ANSI/ASME NQA-1 are referenced as guides.11. Keywords11.1 concentrates; uranium ore; yellow cakeTABLE 1 Impurities and Maximum Concentration LimitsImpurityMaximum Concentration Limit (Mass %, UraniumBasis)ALimit WithoutPenaltyBLimit Without Reject
24、ionCAs 0.05 0.10B 0.005 0.10Ca 0.05 1.00Carbonate 0.20 0.50F 0.01 0.10HalogensD0.05 0.10Fe 0.15 1.00Mg 0.02 0.50MoistureE2.0 5.0Mo 0.10 0.30P 0.10 0.70K 0.20 3.00Si(calculated as SiO2) 0.50 2.50Na 0.50 7.50S 1.00 4.00Th 1.00 2.50Ti 0.01 0.05V 0.06 0.30Zr 0.01 0.10234U56F62FAExcept as specified other
25、wise.BSurcharges may apply to concentrate having impurities exceeding these limits,CThese limits are based on commonly used ore compositions and processingtechnology and can vary when agreed upon in advance among all parties.DExclusive of fluorine.EAs determined by the sampling facility.Fmicrograms
26、per gram of total uranium (g/gU). Editorially corrected.C967082Copyright by ASTM Intl (all rights reserved); Wed Nov 5 02:32:51 EST 2008Downloaded/printed byGuo Dehua (CNIS) pursuant to License Agreement. No further reproductions authorized.ASTM International takes no position respecting the validit
27、y of any patent rights asserted in connection with any item mentionedin this standard. Users of this standard are expressly advised that determination of the validity of any such patent rights, and the riskof infringement of such rights, are entirely their own responsibility.This standard is subject
28、 to revision at any time by the responsible technical committee and must be reviewed every five years andif not revised, either reapproved or withdrawn. Your comments are invited either for revision of this standard or for additional standardsand should be addressed to ASTM International Headquarter
29、s. Your comments will receive careful consideration at a meeting of theresponsible technical committee, which you may attend. If you feel that your comments have not received a fair hearing you shouldmake your views known to the ASTM Committee on Standards, at the address shown below.This standard i
30、s copyrighted by ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959,United States. Individual reprints (single or multiple copies) of this standard may be obtained by contacting ASTM at the aboveaddress or at 610-832-9585 (phone), 610-832-9555 (fax), or serviceastm.org (e-mail); or through the ASTM website(www.astm.org).C967083Copyright by ASTM Intl (all rights reserved); Wed Nov 5 02:32:51 EST 2008Downloaded/printed byGuo Dehua (CNIS) pursuant to License Agreement. No further reproductions authorized.
