ASTM C753-2016 Standard Specification for Nuclear-Grade Sinterable Uranium Dioxide Powder《核级可烧结二氧化铀粉末的标准规格》.pdf

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1、Designation: C753 16Standard Specification forNuclear-Grade, Sinterable Uranium Dioxide Powder1This standard is issued under the fixed designation C753; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of last revision. A n

2、umber 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 sinterableuranium dioxide (UO2) powder. It re

3、cognizes the diversity of manufacturing methods by which UO2powders are produced and the many special requirements for chemical and physical characterizationthat may be applicable for a particular fuel pellet manufacturing process or imposed by the end userof the powder in a specific reactor system.

4、 It is, therefore, anticipated that the buyer may supplementthis specification with more stringent or additional requirements for specific applications.1. Scope1.1 This specification covers nuclear-grade, sinterable UO2powder. It applies to UO2powder containing uranium (U) ofany235U concentration in

5、 the production of nuclear fuel pelletsfor use in nuclear reactors.1.2 This specification recognizes the presence of repro-cessed U in the fuel cycle and consequently defines isotopiclimits for commercial grade UO2. Such commercial grade UO2is defined so that, regarding fuel design and manufacture,

6、theproduct is essentially equivalent to that made from unrepro-cessed U. UO2falling outside these limits cannot necessarilybe regarded as equivalent and may thus need special provisionsat the fuel fabrication plant or in the fuel design.1.3 This specification does not include provisions for pre-vent

7、ing criticality accidents or requirements for health andsafety. Observance of this specification does not relieve theuser of the obligation to be aware of and conform to allinternational, national, or federal, state, and local regulationspertaining to possessing, shipping, processing, or using sourc

8、eor special nuclear material.1.4 This specification refers expressly to UO2powder be-fore the addition of any die lubricant, binder, or pore former. Ifpowder is sold with such additions or prepared as press feed,sampling procedures, allowable impurity contents, or powderphysical requirements may nee

9、d to be modified by agreementbetween the buyer and the seller.1.5 The values stated in SI units are to be regarded as thestandard. The values given in parentheses are for informationonly.1.6 This standard does not purport to address all of thesafety concerns, if any, associated with its use. It is t

10、heresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory requirements prior to use.2. Referenced Documents2.1 ASTM Standards:2B243 Terminology of Powder MetallurgyB329 Test Method for Apparent Density of Metal

11、Powdersand Compounds Using the Scott VolumeterC696 Test Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear-Grade Uranium Di-oxide Powders and PelletsC859 Terminology Relating to Nuclear MaterialsC996 Specification for Uranium Hexafluoride Enriched toLess Than 5 %235UC12

12、33 Practice for Determining Equivalent Boron Contentsof Nuclear MaterialsE11 Specification for Woven Wire Test Sieve Cloth and TestSievesE105 Practice for Probability Sampling of Materials2.2 ASME Standard:3ASME NQA-1 Quality Assurance Requirements for NuclearFacility Applications1This specification

13、 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 Feb. 1, 2016. Published March 2016. Originallyapproved in 1973. Last previous edition approved in 2009 as

14、C753 04 (2009).DOI: 10.1520/C0753-16.2For 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 Document Summary page onthe ASTM website.3Available from American

15、 Society of Mechanical Engineers (ASME), ASMEInternational Headquarters, Two Park Ave., New York, NY 10016-5990, http:/www.asme.org.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States12.3 Federal Regulation:4Code of Federal Regulations, T

16、itle 10, Chapter 1, NuclearRegulatory Commission, Applicable Parts3. Terminology3.1 DefinitionsDefinitions of terms are as given in Termi-nologies B243 and C859.4. Chemical Composition4.1 Uranium ContentThe U content shall be determinedon a basis to be agreed upon between the buyer and seller.4.2 Ox

17、ygen-to-Uranium Ratio (O/U)The O/U ratio maybe specified as agreed upon between the buyer and seller. Thedetermination of the O/U ratio shall be in accordance with TestMethods C696 or a demonstrated equivalent.4.3 Impurity ContentThe impurity content shall not ex-ceed the individual element limit sp

18、ecified in Table 1 onaUbasis. Total non-volatile oxide impurity content (see Table 1and other impurity elements not having associated limits inTable 2) shall not exceed 1500 g/gU. If an element analysis isreported as “less than” a given concentration, this “less than”value shall be used in the deter

19、mination of total impurities.Impurity elements measured and their associated limits maydiffer from what is listed in this specification agreed uponbetween the buyer and seller.4.4 Moisture ContentThe moisture content shall not ex-ceed 0.50 weight percent of the powder.4.5 Isotopic Content:4.5.1 For

20、UO2powder with an isotopic content of235Ubelow 5 %, the isotopic limits of Specification C996 shallapply, unless otherwise agreed upon between the buyer and theseller. If the236U content is greater than Enriched CommercialGrade UF6requirements, the isotopic analysis requirements ofSpecification C996

21、 shall apply. The specific isotopic measure-ments required by Specification C996 may be waived, pro-vided that the seller can demonstrate compliance with Speci-fication C996, for instance, through the sellers qualityassurance records.4.5.2 For UO2powder that does not have an assay in therange set fo

22、rth in 4.5.1, the isotopic requirements shall be asagreed upon between the buyer and the seller.4.6 Equivalent Boron ContentFor thermal reactor use, thetotal equivalent boron content (EBC) shall not exceed 4.0 g/gon a U basis. For purpose of EBC calculation B, Gd, Eu, Dy,Sm, and Cd shall be included

23、 in addition to elements listed inTable 1. The method of performing the calculation shall be asindicated in Practice C1233. For fast reactor use, the abovelimitation on EBC does not apply.5. Physical Properties5.1 Cleanliness and WorkmanshipThe UO2powder shallbe free of visible fragments of foreign

24、matter.5.2 Particle SizeUO2powder particle size limits andmethod of determination shall be as agreed upon between thebuyer and seller.As an example, the fraction of a representativesample not passing through a 425-m (No. 40) standard sieveconforming to Specification E11 shall be reported to the buye

25、r.5.3 Bulk DensityThe bulk density of UO2powder willdepend on the processing method. Unless otherwise agreedupon between the buyer and seller, the bulk density shall be aminimum of 0.625 g/cm3as determined by Test Method B329,or an agreed upon alternative.5.4 SinterabilityTest pellets shall be produ

26、ced and mea-sured in accordance with a sintering performance test agreedupon between the buyer and seller. A sinterability performancetest described in Appendix X1 is presented as a guide.6. Sampling6.1 A lot is defined as a quantity of UO2powder that isuniform in isotopic, chemical, physical, and s

27、interability char-acteristics.6.2 The identity of a lot shall be retained throughout itsprocessing history.4Available from U.S. Government Printing Office, Superintendent ofDocuments, 732 N. Capitol St., NW, Washington, DC 20401-0001, http:/www.access.gpo.gov.TABLE 1 Impurity Elements and Maximum Co

28、ncentration LimitsElementBMaximum ConcentrationLimit of Uranium, g/gUAluminum (Al) 300Carbon (C) 100Calcium (Ca) + magnesium (Mg) 200Chlorine (Cl) 100Chromium (Cr) 200Cobalt (Co) 100Copper (Cu) 250Fluorine (F) 100Iron (Fe) 250Lead (Pb) 250Manganese (Mn) 250Molybdenum (Mo) 250Nickel (Ni) 200Nitrogen

29、(N) 200Phosphorus (P) 250Silicon (Si) 300Tantalum (Ta) 250ThoriumA(Th) 10Tin (Sn) 250Titanium (Ti) 250Tungsten (W) 250Vanadium (V) 250Zinc (Zn) 250AThorium is primarily of concern because of the reactor production of233U.BAny additional potential impurities, added by the fabrication process for exam

30、ple,beyond those listed here shall be evaluated (for example, in terms of equivalentboron) and associated limits established and agreed upon between the buyer andseller.TABLE 2 Additional Impurity ElementsElementBeryllium (Be) Manganese (Mn)Bismuth (Bi) Niobium (Nb)Boron (B) Potassium (K)Cadmium (Cd

31、) Silver (Ag)Dysprosium (Dy) Samarium (Sm)Europium (Eu) Sodium (Na)Gadolinium (Gd) Sulfur (S)Indium (In) Zirconium (Zr)Lithium (Li)C753 1626.3 A powder lot shall form the basis for defining samplingplans used to establish conformance to this specification.6.4 Sampling plans and procedures shall be m

32、utually agreedupon by the buyer and the seller. Analytical confirmation ofsampling plans shall be documented as part of the manufac-turers quality assurance and nuclear materials control andaccountability program.6.5 UO2may be hygroscopic and retain sufficient waterafter exposure to a moist atmosphe

33、re to cause detectable errors.Sample, weigh, and handle the sample under conditions thatwill ensure that the sample is representative of the lot.7. Test Methods7.1 The seller shall test the sample to ensure conformance ofthe powder to the requirements of Sections 4 and 5.7.1.1 All chemical analyses

34、shall be performed on portionsof the representative sample. Analytical chemistry methodsused shall be in accordance with Test Methods C696 ordemonstrated equivalent methods agreed upon between thebuyer and seller.7.2 Lot AcceptanceAcceptance testing may be performedby the buyer on either the sample

35、provided by the seller or asample taken at the buyers plant by sampling one or moreindividual containers with a sample thief. Practice E105 isreferenced as a guide. Acceptance shall be on a lot basis,consistent with Section 6, and shall be contingent upon thematerial properties meeting the requireme

36、nts of Sections 4 and5.7.3 Referee MethodThe buyer and seller shall agree to athird party as a referee in the event of a dispute in analyticalresults.8. Certification8.1 The seller shall provide to the buyer documents certify-ing:8.1.1 The isotopic content and identity of the startingmaterial lot an

37、d8.1.2 That the powder meets all the requirements of Sec-tions 4 through 6.8.2 Test data on the following characteristics shall besupplied upon request:8.2.1 Uranium isotopic content,8.2.2 Uranium content,8.2.3 Individual impurity levels,8.2.4 Moisture content,8.2.5 Sinterability test results,8.2.6

38、O/U ratio,8.2.7 Particle size, and8.2.8 Bulk density.9. Packaging and Package Marking9.1 UO2powder shall be packaged in sealed containers toprevent loss of material and undue contamination from air orthe container materials. The exact size and method of packag-ing shall be as agreed upon by the buye

39、r and seller.9.2 Each container shall bear, as a minimum, a label on thelid and side with the following information:9.2.1 Sellers name,9.2.2 Material in container,9.2.3 Lot number,9.2.4 Uranium enrichment,9.2.5 Gross, tare, net oxide weights,9.2.6 Uranium weight,9.2.7 Purchase order number, and9.2.8

40、 Container ( ) of ( ).10. Quality Assurance10.1 Quality Assurance requirements shall be as agreedupon between the buyer and seller when specified in thepurchase order. Code of Federal Regulations, Title 10, Part 50,Appendix B and ASME NQA-1 are referenced as guides.11. Keywords11.1 nuclear fuel; pow

41、der; uranium dioxideAPPENDIX(Nonmandatory Information)X1. SINTERABILITY TESTX1.1 PurposeX1.1.1 The purpose of the sinterability test is to verify thefabricability of each lot of UO2powder.Although not required,it is desirable to simulate the buyers pellet fabrication processto improve the predictabi

42、lity of the powder. A suggestedsinterability test follows.X1.2 Fabrication of Test PelletsX1.2.1 Preparation of Test PelletsCold press powder withthe addition of agreed upon quantities of additive to produce atleast fifteen green pellets within a predetermined density rangeapproximating the buyers t

43、arget range. The density of eachgreen pellet shall vary no more than 60.5 % theoretical density(TD) from the average of the required test pellets. The type ofpellet press, pressing conditions, die geometry (that is, taper,dishing, etc.), use and quantity of any lubricant or additive (ifused), powder

44、 preconditioning, dwell time, and any otherrelevant pressing conditions shall be approved by the buyer.Report the green density and pressing pressure for each pellet.C753 163X1.2.2 The diameter and length-to-diameter ratio of theunsintered test pellets shall be approximately that of thebuyers unsint

45、ered production pellets. The length of eachunsintered pellet shall vary no more than 60.5 mm (60.02 in.).X1.2.3 Sinter the pellets as one batch in reducing atmo-sphere (for example, hydrogen, or dissociated ammonia) at apredetermined temperature set point (typically 1625 to 1750C,with a temperature

46、control of 625C) for 2 to 6 h, approxi-mating the buyers sintering conditions. The type of furnaceused, atmosphere including dew point, and actual sinteringcycle shall be as agreed upon between the buyer and the seller.X1.2.4 Once established, all of the parameters of this testshall remain unchanged

47、 throughout all lots of the order.X1.3 Density DeterminationX1.3.1 Determine the geometrical density of the unsinteredand sintered, but unground pellets as follows:X1.3.1.1 DiameterRecord the average of four readingstaken to the nearest 0.005 mm (0.0002 in.) at equally spacedintervals along the leng

48、th of the pellet using a blade microm-eter or equivalent gauge.X1.3.1.2 LengthRecord the average of three readingstaken to the nearest 0.005 mm (0.0002 in.) from end to end ofthe pellet at equally spaced intervals along a longitudinallybisecting plane using a micrometer or equivalent gauge.X1.3.1.3

49、WeightRecord the pellet weight to the nearest0.001 g.X1.3.1.4 DensityCalculate the density of each pellet to thenearest 0.01 g/cm3. The geometric density calculation shouldaccount for known biases due to pellet geometry effects andshould be qualified by demonstrated equivalency with animmersion technique for sintered pellets.X1.3.2 Alternatively, the density of the sintered pellet maybe obtained by an immersion technique or demonstratedequivalent method as agreed upon between the buyer and theseller.X1.4 Sintered Pellet Performance TestX1.4.1 Make