ASTM C967-2013 Standard Specification for Uranium Ore Concentrate《铀矿石浓缩物的标准规格》.pdf

1、Designation: C967 13Standard 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 indi

2、cates 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

3、 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 specifi

4、cation 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 materia

5、l (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:2C859 Terminology Relating to Nuclear MaterialsC1022 Test Methods for Chemical and Atomic AbsorptionAnalysis of Uranium-O

6、re ConcentrateC1075 Practices 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,

7、 Nuclear Regulatory Commis-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 Facilities3

8、2.3 ANSI Standard:5ANSI/ASME NQA-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 o

9、f 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 1.1This specification is under the jurisdiction of ASTM Committee C26 onNuclear Fuel Cycle and is the direc

10、t responsibility of Subcommittee C26.02 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

11、, 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 the Nuclear Regulatory Commission, Washington, DC, 20555-0001, www.nrc.gov.4Available from the Mate

12、rials Transportation Bureau, 400 Seventh St.,Washington, 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

13、 States1NOTE 1For ore concentrate from verifiable source (for example,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

14、mass % on a uranium basis.4.4 Extractable OrganicDepending on the conversionprocess (dry route vs. wet 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 sh

15、all be used.4.5 Impurity ContentThe impurity content shall be lessthan the maximum 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 s

16、hould be aware that their level can vary.Determination of these elements and the 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 of14 in.5.2 Ability to FlowConcent

17、rate 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 concentrates or to th

18、eequipment 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 representative sample, of a size sufficient to performthe tests prescribed in Sections 4 and 5, shall be taken fromeach lot.6.3 Practices C1075 is referenced

19、as a guide.7. Test Methods7.1 All chemical analyses shall be performed on portions ofthe representative sample prepared in accordance with Section6. Analytical chemistry methods shall be in accordance withTest Methods C1022, C1380 or as otherwise agreed.8. Certification8.1 When specified in the purc

20、hase order or contract,certification shall be furnished that the material was sampledand tested in accordance with this specification and has beenfound 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

21、 Marking9.1 Uranium ore concentrate shall be packaged and shippedin drums having lids fitted with watertight sealing rings. Thelids shall be attached to the drums in a manner that minimizesTABLE 1 Impurities and Maximum Concentration LimitsImpurityMaximum Concentration Limit (Mass %,Uranium Basis)AL

22、imit WithoutPenaltyBLimit Without RejectionCAs 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 0.10 2.50Ti 0.01 0.05V 0.06 0.30Zr 0.01

23、0.10234U56F62FAExcept as specified otherwise.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 determin

24、ed by the sampling facility. In case of uranium peroxide, moistureshall be understood as “free moisture”; determined by calcinations at 110C.Fmicrograms per gram of total uranium (g/gU).C967 132loss of concentrate in the event of mishandling. Shippingcontainers shall meet applicable regulatory requi

25、rements. 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 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 ( ).9.3 Urani

26、um Ore Concentrate suppliers should be awarethat decomposition of peroxides can lead to pressurization oftransport containers. Such condition may be noncompliant withtransport regulations.10. Quality Assurance10.1 Quality assurance requirements shall be as agreed uponbetween the buyer and the seller

27、 when specified in the purchaseorder. Code of Federal Regulations Title 10, Part 50, AppendixB and ANSI/ASME NQA-1 are referenced as guides.11. Keywords11.1 concentrates; uranium ore; yellow cakeASTM International takes no position respecting the validity of any patent rights asserted in connection

28、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 to revision at any time by the responsible te

29、chnical 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 Headquarters. Your comments will receive careful consider

30、ation 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 is copyrighted by ASTM International, 100 Barr

31、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). Permission rights to photocopy the standard may also be secured from the ASTM website (www.astm.org/COPYRIGHT/).C967 133