ASTM C1334-2005(2016)e1 Standard Specification for Uranium Oxides with a&x2009 235U Content of Less Than 5&x2009 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Diox.pdf

1、Designation: C1334 05 (Reapproved 2016)1Standard Specification forUranium Oxides with a235U Content of Less Than 5 % forDissolution Prior to Conversion to Nuclear-Grade UraniumDioxide1This standard is issued under the fixed designation C1334; the number immediately following the designation indicate

2、s the year oforiginal adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon () indicates an editorial change since the last revision or reapproval.1NOTEEditorially updated organization name of referenced d

3、ocument in 2.2 in January 2016.1. Scope1.1 This specification covers uranium oxides, includingprocessed byproducts or scrap material (powder, pellets, orpieces), that are intended for dissolution into uranyl nitratesolution meeting the requirements of Specification C788 priorto conversion into nucle

4、ar grade UO2powder with a235Ucontent of less than 5 %. This specification defines the impurityand uranium isotope limits for such urania powders that are tobe dissolved prior to processing to nuclear grade UO2asdefined in Specification C753.1.2 This specification provides the nuclear industry with a

5、general standard for such uranium oxide powders. It recognizesthe diversity of conversion processes and the processes towhich such powders are subsequently to be subjected (forinstance, by solvent extraction). It is therefore anticipated thatit may be necessary to include supplementary specification

6、limits by agreement between the buyer and seller.1.3 The scope of this specification does not comprehen-sively cover all provisions for preventing criticality accidents,for health and safety, or for shipping. Observance of thisspecification does not relieve the user of the obligation toconform to al

7、l international, national, state and local regula-tions for processing, shipping, or any other way of using uraniapowders (see 2.2 and 2.3).2. Referenced Documents2.1 ASTM Standards:2C696 Test Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear-Grade Uranium Di-oxide Pow

8、ders and PelletsC753 Specification for Nuclear-Grade, Sinterable UraniumDioxide PowderC788 Specification for Nuclear-Grade Uranyl Nitrate Solu-tion or CrystalsC799 Test Methods for Chemical, Mass Spectrometric,Spectrochemical, Nuclear, and Radiochemical Analysis ofNuclear-Grade Uranyl Nitrate Soluti

9、onsC859 Terminology Relating to Nuclear MaterialsC996 Specification for Uranium Hexafluoride Enriched toLess Than 5 %235UC1233 Practice for Determining Equivalent Boron Contentsof Nuclear MaterialsE105 Practice for Probability Sampling of Materials2.2 ASME Standard:3ASME NQA-1 QualityAssurance Requi

10、rements for NuclearFacility Applications2.3 U.S. Government Document:4Federal Regulations Title 10, (Energy) Part 50, DomesticLicensing of Production and Utilization Facilities3. Terminology3.1 Definitions of Terms Specific to This Standard:3.1.1 Terms shall be defined in accordance with Terminol-og

11、y C859, except for the following:3.1.2 Commercial Grade Uranium Oxide, nany oxide ofuranium made from unirradiated uranium. It is recognizedsome contamination with reprocessed uranium may occurduring routine processing; this is acceptable provided that thespecification for Commercial Grade Uranium O

12、xide as setforth in 4.1 is met.1This specification is under the jurisdiction of ASTM Committee C26 onNuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fueland Fertile Material Specifications.Current edition approved Jan. 15, 2016. Published January 2016. Originallyapprove

13、d in 1996. Last previous edition approved in 2010 as C1334 05 (2010).DOI: 10.1520/C1334-05R16E01.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Docum

14、ent Summary page onthe ASTM website.3Available from American Society of Mechanical Engineers (ASME), ASMEInternational Headquarters, Two Park Ave., New York, NY 10016-5990, http:/www.asme.org.4Available from U.S. Government Printing Office Superintendent of Documents,732 N. Capitol St., NW, Mail Sto

15、p: SDE, Washington, DC 20401, http:/www.access.gpo.gov.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States13.1.3 scrap, nin the nuclear industry, residues that containsufficient quantities of source or special nuclear material to beworthy

16、 of recovery.4. Isotopic Content4.1 For Commercial Grade Uranium Oxide with an isotopiccontent of235U between that of natural uranium and 5 %, theisotopic and radionuclide limits of Specification C996 shallapply. The specific isotopic and radionuclide measurementsrequired by Specification C996 may b

17、e waived, provided thatthe seller can demonstrate compliance through, for instance,the sellers quality assurance records.4.2 For commercial uranium oxides not having an assay inthe range set forth in 4.1, the isotopic requirements shall be asagreed upon between the buyer and seller.5. Physical and C

18、hemical Requirements5.1 Uranium ContentThe uranium content shall be deter-mined using methods described in Test Methods C696 andC799, or as agreed upon between the buyer and seller. Basedon the oxygen-to-uranium ratio, the minimum total uraniumcontent shall also be agreed upon between the buyer and

19、seller.5.2 Impurity ContentThe impurity content shall not ex-ceed the individual element limits specified in Table 1. Thesummation of the contribution of each of the impurity elementslisted in Table 1 shall not exceed 1000 g/gU. The impuritycontent shall be determined using methods described in Test

20、Methods C696 or as agreed upon between the buyer and seller.If the Table 1 specifications are not met, and processing beyondsimple dissolution is anticipated, the concentrations of carbonand toxic elements such asAg, Cr, Pb, Hg, Se, Sb, andAs shallbe reported for information. Analysis requirements m

21、ay bewaived provided the seller can characterize the material, forexample, through the sellers QA records.5.3 Equivalent Boron ContentThe total equivalent boroncontent (EBC) shall not exceed 2.0 g/gU. The list of elementsto be considered in the EBC calculation shall be as recom-mended in Practice C1

22、233. The method of performing thecalculation shall be as indicated in Practice C1233.5.4 If the concentrations of any of the elements used in thecalculations in 5.2 are reported as a less-than value, thisless-than value shall be used for any further calculationsinvolving the concentration of this el

23、ement.5.5 Moisture ContentThe moisture content of the uraniumoxide shall not exceed 1 % by weight unless otherwise agreedupon by the buyer and seller.5.6 Ability to FlowThe Commercial Grade Uranium Ox-ide shall be sufficiently free-flowing to permit sampling andpowder handling.5.7 Particle SizeParti

24、cle size, size distribution andmethod of determination shall be as agreed upon between thebuyer and seller. Packing or agglomeration during shipping, orboth, may be a concern.5.8 DissolvabilityAt the buyers request, a dissolvabilitytest shall be performed by a procedure and to a specification asmutu

25、ally agreed upon between buyer and seller. The testparameters (such as time, temperature, nitric acid molarity) andcharacteristics to be measured (such as dissolution rate,insolubles, foam generation) shall be defined by agreementbetween the buyer and seller.6. Lot Requirements6.1 A lot is defined a

26、s a quantity of Commercial GradeUranium Oxide powder that is uniform in isotopic, chemical,and flowability characteristics.6.2 The identity of a lot shall be retained throughout.6.3 A powder lot shall form the basis for defining samplingplans used to establish conformance to this specification.6.4 S

27、ampling plans shall be mutually agreed upon by thebuyer and seller. A suggested sampling procedure is given inAppendix X1.7. Testing and Certification7.1 The material shall be sampled as described in AppendixX1 and tested to ensure conformance of the powder to therequirements as agreed upon between

28、the buyer and the seller.7.2 The seller, as above, shall provide to the buyer docu-ments certifying that the material meets all the requirements ofSections 4, 5, and 6.7.3 Lot AcceptanceAcceptance testing may be performedby the buyer on either the sample provided by the seller or ona sample taken at

29、 the buyers plant by sampling one or moreindividual containers with a thief. Practice E105 is referencedas a guide. Acceptance shall be on a lot basis and shall becontingent upon the material properties meeting the require-ments of Sections 4, 5, and 6.7.4 Referee MethodThe buyer and seller may agre

30、e to athird party as a referee in the event of a dispute in analyticalresults.TABLE 1 Impurity Elements and Maximum Concentration LimitsElementMaximum ConcentrationLimit (g/gU)Aluminum 150Barium 5Bismuth 3Calcium and Magnesium 150Chlorine 100Chromium 100Cobalt 80Copper 100Fluorine 100Iron 150Lead 40

31、Manganese 50Molybdenum 200Nickel 80Phosphorus 100Silicon 200Sodium 20Tantalum 200Thorium 10Tin 50Titanium 50Tungsten 100Vanadium 10Zinc 20C1334 05 (2016)128. Packaging and Marking8.1 Uranium oxide powder shall be packaged in sealedcontainers to prevent loss of material and undue contaminationfrom ai

32、r or to the container materials. The exact size andmethod of packaging shall be as agreed upon between thebuyer and seller.8.2 Each container shall bear, as a minimum, a label on thelid and side with the following information:8.2.1 Sellers name,8.2.2 Material in container,8.2.3 Lot number,8.2.4 Uran

33、ium enrichment,8.2.5 Gross, tare, net oxide weights,8.2.6 Uranium weight,8.2.7 Purchase order number (or equivalent), and8.2.8 Container()of().9. Quality Assurance9.1 Quality assurance requirements shall be as agreed uponbetween the buyer and seller when specified in the purchaseorder. Code of Feder

34、al Regulations Title 10, Part 50, AppendixB and NQA-1 are referenced as guides.10. Keywords10.1 nuclear fuel; uranium oxide; uranium oxide dissolutionAPPENDIX(Nonmandatory Information)X1. SAMPLINGX1.1 Uranium oxide may be hygroscopic and retain suffi-cient water after exposure to a moist atmosphere

35、to causedetectable error. Sample, weigh, and handle the sample underconditions that will ensure that the sample is representative ofthe lot.X1.2 Take a representative sample of powder from each lotfor the purpose of determining chemical properties.X1.3 A lot sample shall be of sufficient size to per

36、formquality assurance testing at the sellers plant, acceptancetesting at the buyers plant, and referee tests in the event theybecome necessary.X1.4 Package the lot sample for acceptance testing at thebuyers plant in a separate container, clearly identify by lotnumber, and ship with the lot. Clearly

37、identify the refereesample and retain it at the manufacturers (if someone otherthan the seller) plant until the lot has been formally accepted bythe buyer.X1.5 Prepare the lot sample by blending and splitting thecontainer samplesX1.6 To obtain a container sample, take specimens with athief at random

38、 locations along a randomly chosen verticaltraverse through each container selected at random to besampled. Then blend the thief samples from the selectedcontainers and split down to the required size.X1.7 The number of containers so sampled shall be 5 +(n/10) where n is the total number of containe

39、rs per lot roundedto the nearest decade. If there are five or fewer containers perlot, each container shall be so sampled.X1.8 Alternatively, an auto-sampler can be used to obtainsamples during emptying or filling of the container.ASTM International takes no position respecting the validity of any p

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42、mments 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 is copyrigh

43、ted 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). Permission rights to photocopy the standard may also be secured from the Copyright Clearance Center, 222Rosewood Drive, Danvers, MA 01923, Tel: (978) 646-2600; http:/ 05 (2016)13