ASTM C967-2002a Standard Specification for Uranium Ore Concentrate《铀矿浓缩物的标准规范》.pdf

《ASTM C967-2002a Standard Specification for Uranium Ore Concentrate《铀矿浓缩物的标准规范》.pdf》由会员分享，可在线阅读，更多相关《ASTM C967-2002a Standard Specification for Uranium Ore Concentrate《铀矿浓缩物的标准规范》.pdf（3页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: C 967 02aStandard 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 i

2、ndicates the year of last reapproval. Asuperscript epsilon (e) indicates an editorial change since the last revision or reapproval.e1NOTETable 1 was corrected editorially and the yeardate was changed on August 22, 2002.INTRODUCTIONThis specification is intended to provide the nuclear industry with a

3、 general standard for uraniumore concentrate. Material conforming to this specification will 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 specificatio

4、n covers uranium ore concentrate con-taining a minimum of 65 mass % uranium.1.2 This specification 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, stat

5、e, and local regula-tions pertaining to possessing, shipping, or using sourcenuclear material (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:C 859 Terminology Relating to

6、 Nuclear Materials2C 1022 Test Methods for Chemical and Atomic AbsorptionAnalysis of Uranium-Ore Concentrate2C 1075 Practices for Sampling Uranium-Ore Concentrate2C 1380 Test Method for the Determination of UraniumContent and Isotopic Composition by Isotope DilutionMass Spectrometry22.2 U.S. Governm

7、ent Documents:Nuclear Materials Licensing Code of Federal RegulationsTitle 10, Chapter 1, Nuclear Regulatory Commission3Nuclear Materials Licensing Code of Federal Regulations,Title 49, Transportation Chapter 1, Materials Transporta-tion Bureau4Nuclear Materials Licensing Code of Federal Regulations

8、,Energy Part 50 (10CFR 50) Licensing of Domestic Pro-duction and Utilization Facilities32.3 ANSI Standard:ANSI/ASME NQA-1 Quality Assurance Requirements forNuclear Facility Applications53. Terminology Definitions3.1 Except as otherwise defined herein, definitions of termsare as given in Terminology

9、C 859.4. Chemical Composition4.1 Uranium ContentThe uranium content, as received,shall be a minimum of 65 mass %.4.2 Isotopic ContentThe isotopic content shall be that ofnaturally occurring uranium (0.7105 6 0.0005 g235U per 100g. The234U content shall not exceed the limits in Table 1.4.3 Insoluble

10、UraniumThe uranium insoluble in nitricacid shall be a maximum of 0.10 mass % on a uranium basis.4.4 Extractable OrganicThe extractable organic shall be amaximum of 0.10 weight % on an as-received basis of anundried sample.4.5 Impurity ContentThe impurity content shall be lessthan the maximum limits

11、specified in Table 1. The seller shouldadvise all parties of the presence of toxic elements such as Ag,As, Ba, Cd, Cr(VI), Hg, Pb, and Se in the uranium oreconcentrate.1This specification is under the jurisdiction of ASTM Committee C26 onNuclear Fuel Cycle and is the direct responsibility of Subcomm

12、ittee C26.02 on Fueland Fertile Material Specifications.Current edition approved Aug. 22, 2002. Published August 2002. Originallypublished as C 967 81. Last previous edition C 967 02.2Annual Book of ASTM Standards, Vol 12.01.3Available from the Nuclear Regulatory Commission, 1717 H Street, N. W.,Was

13、hington, DC 20555.4Available from the Materials Transportation Bureau, 400 Seventh St., Wash-ington, DC, 20590.5Available from American National Standards Institute, 11 W. 42nd St., 13thFloor, New York, NY 10036.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA

14、 19428-2959, United States.5. Physical 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 mat

15、e-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 theequipment used in such sampling.6. Sampling6.1 The lot size and number of tests (and retests whenrequired) shall

16、 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 C 1075 is referenced as a guide.7. Test Methods7.1 All chemical analyses shall be performed on portions ofthe representative sample p

17、repared in accordance with Section6. Analytical chemistry methods shall be in accordance withTest Methods C 1022, C 1380 or as otherwise agreed.7.1.1 The seller should advise all parties of the presence oftoxic elements such as Ag, As, Ba, Cd, Cr(VI), Hg, Pb, and Sein the uranium ore concentrate.8.

18、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 beenfound to meet the requirements. When specified in the pur-chase order or contract, a report of the test results

19、 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 attached to the drums in a manner that minimizesloss of concentrate in the event of mishandling. Shippingcontainers

20、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 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, a

21、nd9.2.5 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 Federal Regulations Title 10, Part 50, AppendixB and ANSI/ASME NQA-1 are referenced as guides.11. Keywords11.1 co

22、ncentrates; uranium ore; yellow cakeTABLE 1 Impurities and Maximum Concentration LimitsImpurityMaximum Concentration Limit (Mass %, UraniumBasis)ALimit 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 0.50M

23、oistureE2.0 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 otherwise.BSurcharges may apply to concentrate having impurities exceeding these limits,CThese limits are based on com

24、monly 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 per gram of total uranium (g/gU). Editorially corrected.C 967 02a2ASTM International takes no position respecting

25、 the validity 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 standar

26、d is subject 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

27、 Headquarters. 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.Thi

28、s standard is 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).C 967 02a3