ASTM C967-2012 Standard Specification for Uranium Ore Concentrate 《铀矿石浓缩物的标准规格》.pdf

1、Designation:C96708 Designation: C967 12Standard 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

2、in parentheses indicates 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

3、 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 specification covers uranium ore concentrate containing a minimum of 65 mass % uraniu

4、m.1.2 This specification does not include requirements for health and safety. Observance of this specification does not relieve theuser of the obligation to be aware of and conform to all applicable international, national, state, and local regulations pertainingto possessing, shipping, or using sou

5、rce nuclear material (see 2.2).1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.2. Referenced Documents2.1 ASTM Standards:2C859 Terminology Relating to Nuclear MaterialsC1022 Test Methods for Chemical and Atomic Absorption

6、 Analysis of Uranium-Ore ConcentrateC1075 Practices for Sampling Uranium-Ore ConcentrateC1380 Test Method for the Determination of Uranium Content and Isotopic Composition by Isotope Dilution MassSpectrometry2.2 U.S. Government Documents:Nuclear Materials Licensing Code of Federal Regulations, Energ

7、y Title 10, Chapter 1, Nuclear Regulatory Commission3Nuclear Materials Licensing Code of Federal Regulations, Title 49, Transportation Chapter 1, Materials Transportation Bureau4Nuclear Materials Licensing Code of Federal Regulations, Energy Part 50 (10CFR 50) Licensing of Domestic Production andUti

8、lization Facilities32.3 ANSI Standard:5ANSI/ASME NQA-1 Quality Assurance Requirements for Nuclear Facility Applications3. Terminology Definitions3.1 Except as otherwise defined herein, definitions of terms are as given in Terminology C859.4. Chemical Composition4.1 Uranium ContentThe uranium content

9、, as received, shall be a minimum of 65 mass %.4.2 Isotopic ContentThe isotopic content shall be that of naturally occurring uranium (0.711 6 0.001 g235U per 100 g (seeNote 1). The234U content shall not exceed the limits in Table 1.NOTE 1For ore concentrate from verifiable source (for example, throu

10、gh the sellers quality assurance records), the235U analysis is not normally1This specification is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel and FertileMaterial Specifications.Current edition approved Jan.June 1,

11、 2008.2012. Published January 2008.July 2012. Originally approved in 1981. Last previous edition approved in 20022008 asC96702a.C967 08. DOI: 10.1520/C0967-08.10.1520/C0967-12.2For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at serviceastm.org. F

12、or Annual Book of ASTM Standardsvolume information, refer to the standards Document Summary page on the ASTM website.3Available from the Nuclear Regulatory Commission, Washington, DC, 20555-0001, www.nrc.gov.4Available from the Materials Transportation Bureau, 400 Seventh St., Washington, DC, 20590.

13、5Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New York, NY 10036, http:/www.ansi.org.1This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Be

14、causeit may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current versionof the standard as published by ASTM is to be considered the official document.Copyright ASTM International, 100

15、 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.required unless otherwise agreed upon between the buyer and seller.4.3 Insoluble UraniumThe uranium insoluble in nitric acid shall be a maximum of 0.10 mass % on a uranium basis.4.4 Extractable OrganicDepending on the c

16、onversion process (dry route vs. wet route), the need for measurement ofextractable organic shall be agreed upon between buyer and seller (see Note 2).NOTE 2If a measurement is requested, a limit of 0.1 g per 100 g of ore concentrate shall be used.4.5 Impurity ContentThe impurity content shall be le

17、ss than 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 should be aware that their level can vary.Determination of thes

18、e elements and the analytical frequency may 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 FlowConcentrate shall be sufficiently free-flowing to permit sampling.5

19、.3 Foreign MatterConcentrate shall be free of all materials and objects that: (a) are not produced as a constituent ofconcentrates in the milling of uranium ore, or, (b) would or could be detrimental to the sampling of concentrates or to theequipment used in such sampling.6. Sampling6.1 The lot size

20、 and number of tests (and retests when required) shall be as mutually agreed.6.2 A representative sample, of a size sufficient to perform the tests prescribed in Sections 4 and 5, shall be taken from eachlot.6.3 Practices C1075 is referenced as a guide.7. Test Methods7.1 All chemical analyses shall

21、be performed on portions of the representative sample prepared in accordance with Section 6.Analytical chemistry methods shall be in accordance with Test Methods C1022, C1380 or as otherwise agreed.8. Certification8.1 When specified in the purchase order or contract, certification shall be furnished

22、 that the material was sampled and testedin accordance with this specification and has been found to meet the requirements. When specified in the purchase order orTABLE 1 Impurities and Maximum Concentration LimitsImpurityMaximum Concentration Limit (Mass %,Uranium Basis)ALimit WithoutPenaltyBLimit

23、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 1.00 2.50Ti 0.01 0.05V 0.06 0.30Zr 0.01 0.10234U 56F62F234U 56F62F

24、AExcept 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 determined by the samp

25、ling facility. In case of uranium peroxide, moistureshall be understood as “free moisture.”Fmicrograms per gram of total uranium (g/gU).Editorially corrected.C967 122contract, a report of the test results shall be furnished.9. Packaging and Package Marking9.1 Uranium ore concentrate shall be package

26、d and shipped in drums having lids fitted with watertight sealing rings. The lidsshall be attached to the drums in a manner that minimizes loss of concentrate in the event of mishandling. Shipping containers shallmeet applicable regulatory requirements. CFR Title 10 and Title 49 are referenced as gu

27、ides.9.2 Each container shall bear, as a minimum, labels on the lid and side with the following information:9.2.1Sellers name,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 Uranium Ore Concentrate suppliers should

28、 be aware that decomposition of peroxides can lead to pressurization of transportcontainers. Such condition may be noncompliant with transport regulations.10. Quality Assurance10.1 Quality assurance requirements shall be as agreed upon between the buyer and the seller when specified in the purchaseo

29、rder. Code of Federal Regulations Title 10, Part 50, Appendix B 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 with any item mentionedin this

30、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 technical committee and must be r

31、eviewed 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 consideration at a meeting of therespon

32、sible 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 Harbor Drive, PO Box C700, West

33、 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 123