ASTM C833-2001(2008) Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets《烧结二氧化铀钚丸的标准规范》.pdf

1、Designation: C 833 01 (Reapproved 2008)Standard Specification forSintered (Uranium-Plutonium) Dioxide Pellets1This standard is issued under the fixed designation C 833; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of la

2、st revision. A number 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 foruranium-plutonium dioxide pell

3、ets for thermal reactor use. It recognizes the diversity of manufactur-ing methods by which uranium-plutonium dioxide pellets are produced and the many specialrequirements for chemical and physical characterization that may be imposed by the operatingconditions to which the pellets will be subjected

4、 in specific reactor systems. It does not recognize thepossible problems associated with the reprocessing of such pellets. It is, therefore, anticipated that thepurchaser may supplement this specification with additional requirements for specific applications.1. Scope1.1 This specification covers fi

5、nished sintered and ground(uranium-plutonium) dioxide pellets for use in thermal reac-tors. It applies to uranium-plutonium dioxide pellets containingplutonium additions up to 15 % weight. This specification maynot completely cover the requirements for pellets fabricatedfrom weapons-derived plutoniu

6、m.1.2 This specification does not include (1) provisions forpreventing criticality accidents or (2) requirements for healthand safety. Observance of this specification does not relieve theuser of the obligation to be aware of and conform to allapplicable international, federal, state, and local regu

7、lationspertaining to possessing, processing, shipping, or using sourceor special nuclear material. Examples of U.S. governmentdocuments are Code of Federal Regulations Title 10, Part50Domestic Licensing of Production and Utilization Facili-ties; Code of Federal Regulations Title 10, Part 71Packaging

8、and Transportation of Radioactive Material; and Code ofFederal Regulations Title 49, Part 173General Requirementsfor Shipments and Packaging.1.3 The following safety hazards caveat pertains only to thetechnical requirements portion, Section 4, of this specification:This standard does not purport to

9、address all of the safetyconcerns, if any, associated with its use. It is the responsibilityof the user of this standard to establish appropriate safety andhealth practices and determine the applicability of regulatorylimitations prior to use.1.4 The values stated in SI units are to be regarded asst

10、andard. No other units of measurement are included in thisstandard.2. Referenced Documents2.1 ASTM Standards:2C 698 Test Methods for Chemical, Mass Spectrometric, andSpectrochemicalAnalysis of Nuclear-Grade Mixed Oxides(U, Pu)O2)C 753 Specification for Nuclear-Grade, Sinterable UraniumDioxide Powder

11、C 757 Specification for Nuclear-Grade Plutonium DioxidePowder, SinterableC 859 Terminology Relating to Nuclear MaterialsC1165 Test Method for Determining Plutonium byControlled-Potential Coulometry in H2SO4at a PlatinumWorking ElectrodeC 1204 Test Method for Uranium in Presence of Plutoniumby Iron(I

12、I) Reduction in Phosphoric Acid Followed byChromium(VI) TitrationC 1206 Test Method for Plutonium by Iron (II)/Chromium(VI) Amperometric TitrationC 1233 Practice for Determining Equivalent Boron Con-tents of Nuclear MaterialsE 105 Practice for Probability Sampling Of Materials2.2 ANSI Standard:3ANSI

13、/ASME NQA-1 Quality Assurance Requirements for1This 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 Dec. 1, 2008. Published January 2009. Ori

14、ginallyapproved in 1976. Last previous edition approved in 2001 as C 833 01.2For 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 onth

15、e ASTM website.3Available from American National Standards Institute (ANSI), 25 W. 43rd St.,4th Floor, New York, NY 10036, http:/www.ansi.org.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.Nuclear Facility Applications2.3 U.S. Gover

16、nment Documents:4USNRC Regulatory Guide 1.126 An Acceptable Model andRelated Statistical Methods for the Analysis of FuelDensificationCode of Federal Regulations Title 10, Part 50 DomesticLicensing of Production and Utilization FacilitiesCode of Federal Regulations Title 10, Part 71 Packagingand Tra

17、nsportation of Radioactive MaterialCode of Federal Regulations Title 49, Part 173 GeneralRequirements for Shipments and Packaging3. Terminology3.1 DefinitionsDefinitions shall be in accordance withTerminology C 859.4. Technical Requirements4.1 Chemical RequirementsAll chemical analyses shall beperfo

18、rmed on portions of the representative sample prepared inaccordance with Section 6. Analytical chemistry methods shallbe as stated in Test Methods C 698 (latest edition) or demon-strated equivalent as mutually agreed to between the buyer andthe seller.4.1.1 Uranium and Plutonium ContentUnless agreed

19、upon by the buyer and seller, individual powders shall meet therequirements of Specifications C 753 and C 757, which alsoreference Test Methods C 1165, C 1204, and C 1206. Theuranium and plutonium contents combined shall be a minimumof 87.7 % weight on a dry weight basis compensated for theAm-241 co

20、ntent. (Dry weight is defined as the sample weightminus the moisture content). The plutonium content shall bethat specified by the buyer, up to the limits covered in thisspecification (15%).4.1.2 Impurity ContentThe impurity content shall notexceed the individual element limit specified in Table 1 b

21、asedon the heavy metal content (uranium plus plutonium). Thesummation of the contribution of each of the impurity elementslisted in Table 1 shall not exceed 1500 g/g (U + P). If anelement analysis is reported as “less than” a given concentra-tion, this “less than” value shall be used in the determin

22、ation oftotal impurities.NOTE 1Higher impurity limits should be acceptable for restrictedburnups and linear power ratings if there is evidence to substantiate therelaxation. Higher impurity levels of 450 ppm aluminum, 250 ppmcarbon, 250 ppm nitrogen, and 450 ppm silicon have been supported forburnup

23、s of less than 35 000 MWd/t. The extension of the burnup limitmay be determined by agreement between the buyer and seller assupporting data are accumulated.4.1.3 StoichiometryThe oxygen-to-heavy metal ratio ofsintered fuel pellets shall be within the range from 1.98 to 2.02.The nominal value and all

24、owable tolerance shall be agreedupon between the buyer and seller.4.1.4 Moisture ContentThe moisture content limit is in-cluded in the total hydrogen limit (see Table 1).4.1.5 Gas ContentThe gas content, exclusive of moisture,shall not exceed, at Standard Temperature and Pressure (0Cand one atmosphe

25、re), 0.05 L/kg of the heavy metal content.4.1.6 Americium-241 ContentThe americium-241 contentshall be measured by the seller and reported to the buyer. Theamericium-241 content or activity is important in the handlingof UO2-PuO2pellets and will vary with time. The maximumacceptable americium-241 co

26、ntent on a given date along withthe date of analysis shall be agreed upon between the buyer andseller. The dates of separation of plutonium from this isotopeand the analysis dates shall be considered; methods of report-ing shall be agreed upon between the buyer and seller.4.2 Nuclear Requirements:4.

27、2.1 Isotopic ContentThe isotopic content of the ameri-cium, uranium, and plutonium in the (uranium-plutonium)dioxide pellets shall be determined and the date of thedetermination recorded. The234U,235U,236U, and238U contentof the uranium shall be reported as a mass percentage withrespect to total ura

28、nium, and the238Pu,239Pu,240Pu,241Pu, and242Pu content of the plutonium shall be reported on a Pu mass% or on (Pu + Am) mass % basis. The equivalent plutoniumcontent based on uranium and plutonium isotopic concentra-tions shall be as agreed upon between the buyer and seller.4.2.2 Plutonium Equivalen

29、t at a Given Date(uranium-plutonium) dioxide fuel shall be considered as defined by theplutonium content with adjustment (credit or debit) for theactual isotopic composition of plutonium, americium, anduranium. The dates of isotopic analyses in support of thesedeterminations shall be recorded by the

30、 seller and reported tothe buyer. The allowable tolerances tolerances of the plutoniumequivalent content (either as uranium plus plutonium or as theindividual elements) shall be as agreed upon between the buyerand seller.4.2.3 Equivalent Boron ContentFor thermal reactor use,the total equivalent boro

31、n content (EBC) shall not exceed 4.0g/g on a heavy metal basis. The method of performing thecalculation shall be as indicated in Practice C 1233. For thepurposes of EBC calculation, B, Gd, Eu, Dy, Sm, and Cd shallbe included.4.2.4 ReactivityAn integral test of reactivity may beperformed and correlat

32、ed to total EBC by a method agreedupon between the buyer and the seller. If this is done, a totalEBC need not be determined.4Available from U.S. Government Printing Office Superintendent of Documents,732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http:/www.access.gpo.gov.TABLE 1 Impur

33、ity Elements and Maximum Concentration LimitsElementMaximum ConcentrationLimit (g/g of U + Pu)Aluminum 250Carbon 100Calcium + magnesium 200Chlorine 25Chromium 250Cobalt 100Fluorine 25Hydrogen (total from allsources)1.3Iron 500Nickel 250Nitride/nitrogen 75Silicon 250C 833 01 (2008)24.3 Physical Chara

34、cteristics:4.3.1 DimensionsThe dimensions and their tolerances ofthe pellet shall be specified by the buyer. These shall includediameter, length, perpendicularity, and, as required, othergeometric parameters including surface finish.4.3.2 Pellet DensityThe density and tolerance of sinteredpellets sh

35、all be as specified by the buyer. The theoreticaldensity for UO2shall be considered to be 10.96 g/cm3. Thetheoretical density for PuO2shall be considered to be 11.46g/cm3. The theoretical density for the (U, Pu)O2pellets shall becalculated by linear interpolation between these values. Den-sity measu

36、rements shall be made by the method stated inSpecification C 753 (for the geometric method) by an immer-sion density technique, or by demonstrated equivalent methodas mutually agreed upon between the buyer and the seller.4.3.3 Grain Size and Pore MorphologyBecause there isno unique structure for ens

37、uring satisfactory performance, thepellet grain size and pore morphology shall be mutually agreedupon between the buyer and the seller.4.3.4 Plutonium-Oxide Homogeneity and Size:4.3.4.1 Plutonium Homogeneity Within a Pellet LotHomogeneity of the Pu content shall be demonstrated throughanalyses of mu

38、ltiple pellets. Each sample for analysis shouldbe one pellet or a fragment thereof. The range of the equivalentPu content shall not exceed 65.0% relative or 60.2% absolute,whichever is less restrictive. Alternative methods and criteriathat may be agreed upon between the buyer and the seller arepossi

39、ble for evaluation of plutonium homogeneity within a lot.4.3.4.2 Plutonium-Oxide Particle Size and DistributionWithin a PelletThe maximum equivalent diameter of Pu-richparticles shall be less than 400 m. The distribution of Pu-richparticles shall satisfy either of the following requirements: (a)No m

40、ore than 5 % of the nominal PuO2shall be present inPu-rich particles with equivalent diameters of 200 m orgreater, or (b) No more than 5 % of the Pu-rich particles shallbe greater than 100 m in diameter and the average diameter ofPu-rich particles will be less than 50 m. The method fordetermining th

41、e Pu homogeneity and what constitutes a Pu-richparticle shall be agreed upon between the buyer and seller. Thearea percentage and the volume percentage shall be regarded asequivalent provided the homogeneity requirements of 4.3.4.1are satisfied.NOTE 2These limits are based on PuO2that has a nominal

42、65% fissleplutonium content. Smaller particle size may be required for greater fissleplutonium content.4.3.5 Pellet IntegrityPellets shall be inspected accordingto criteria which maintain adequate fuel performance andensure that excessive breakage will not occur during fuel rodloading. Acceptable te

43、st methods include a visual (1X) com-parison with pellet standards or other methods, for example,loadability tests, approved by both the buyer and the seller.4.3.5.1 Surface CracksThe limits for surface cracks are asfollows:(1) Axial Cracks, including those leading to pellet ends12the pellet length.

44、(2) Circumferential Cracks123 of the pellet circumfer-ence.4.3.5.2 ChipsThe limits for chips (missing material) areas follows:(1) Cylindrical Surface Chips(a) Cylindrical Surface Areathe total area of allchips shall be less than 5 % of the pellet cylindrical surfacearea.(b) Maximum Linear Dimension3

45、0 % of the pelletlength.(2) Pellet Ends1/3 of the pellet end surfaces (may beinspected as 1/3 of the missing circumference at the pellet end).4.3.6 Cleanliness and WorkmanshipThe surfaces of fin-ished pellets shall be visually (1X) free of loose chips, oil,macroscopic inclusions, and foreign materia

46、ls.4.4 IdentificationIt shall be possible to identify pellets asto total fissile and total plutonium content by, for example,marking or coding or other administrative controls. Otheridentification can be used (for example, total plutonium and“reference date”).4.5 Irradiation Stability (Densification

47、)An estimate of thefuel pellet irradiation stability shall be obtained unless ad-equate allowance for such effects are factored into the fuel roddesign. The estimate of the stability shall consist of either (a)conformance to the thermal stability test as specified in theapplicable USNRC Regulatory G

48、uide 1.126,or(b) by adequatecorrelation of manufacturing process or microstructure toin-reactor behavior, or both.5. Lot Requirements5.1 A (UO2-PuO2) powder lot is defined as a quantity of(UO2-PuO2) powder that is manufactured to produce uniformisotopic, chemical, physical, and sinterability charact

49、eristics.5.2 A pellet lot is defined as a group of pellets made from asingle (UO2-PuO2) powder lot using one set of blending andpelletizing process parameters.5.3 The identity of a pellet lot shall be retained throughoutprocessing without mixing with other established pellet lots.5.4 Conformance to this specification shall be establishedfor each pellet lot.6. Sampling6.1 Sampling, weighing of the sample, and handling thesample shall be done under conditions that ensure that thesample is representative of the pellet or powder lot. Inparti