1、Designation: C833 13C833 17Standard Specification forSintered (Uranium-Plutonium) Dioxide Pellets for LightWater Reactors1This standard is issued under the fixed designation C833; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the
2、 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.INTRODUCTIONThis specification is intended to provide the nuclear industry with a general standard foruranium-plutonium d
3、ioxide (U, Pu)O2) pellets for thermal light water reactor use. It recognizes thediversity of manufacturing methods by which uranium-plutonium dioxide(U, Pu)O2 pellets areproduced and the many special requirements for chemical and physical characterization that may beimposed by the operating conditio
4、ns to which the pellets will be subjected in specific reactor systems.different light water reactors. It does not recognize the possible problems associated with thereprocessing of such pellets. It is, therefore, anticipated that the purchaser may supplement thisspecification with additional require
5、ments for specific applications.1. Scope1.1 This specification covers finished sintered and ground (uranium-plutonium) dioxide(U, Pu)O2 pellets for use in thermal lightwater reactors. It applies to uranium-plutonium dioxide(U, Pu)O2 pellets containing plutonium additions up to 15 % weight (that15 we
6、ight % (wt%; that is, 0.15 g Pu / g (U+Pu+Am). (U + Pu + Am).1.2 Pellets produced under this specification are available in four grades.1.2.1 Grade R240Pu content of (Pu+Am) (Pu + Am) (that is, g 240Pu / g (Pu+Am) (Pu + Am) is at least 19 %.1.2.2 Grade F240Pu content of (Pu+Am) (Pu + Am) is at least
7、 7 % and less than 19 %.1.2.3 Grade N1240Pu content of (Pu+Am) (Pu + Am) is less than 7 %.1.2.4 Grade N2240Pu /239Pu does not exceed 0.10.1.3 This specification does not include (There is no discussion of or1) provisions provision for preventing criticality accidentsor (incidents, nor are2) requirem
8、ents for health and safety. health and safety requirements, the avoidance of hazards, or shippingprecautions and controls discussed. Observance of this specification does not relieve the user of the obligation to be aware of andconform to all applicable international, federal, state, and local regul
9、ations pertaining to possessing, processing, shipping, or usingsource or special nuclear material. Examples of U.S. government documents are Code of Federal Regulations Title 10, Part50Domestic Licensing of Production and Utilization Facilities; Code of Federal Regulations Title 10, Part 71Packaging
10、 andTransportation of Radioactive Material; and Code of Federal Regulations Title 49, Part 173General Requirements for Shipmentsand Packaging.1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.1.5 The following safety hazards
11、 caveat pertains only to the technical requirements portion, Section 44, of this specification:This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of theuser of this standard to establish appropriate safety and health practi
12、ces and determine the applicability of regulatory limitationsprior to use.1 This 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. 1, 201
13、3Jan. 1, 2017. Published January 2013January 2017. Originally approved in 1976. Last previous edition approved in 20082013 asC833 01C833 13.(2008). DOI: 10.1520/C0833-13.10.1520/C0833-17.This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication
14、of what changes have been made to the previous version. Becauseit 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 consider
15、ed the official document.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States12. Referenced Documents2.1 ASTM Standards:2B243 Terminology of Powder MetallurgyC698 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis
16、of Nuclear-Grade Mixed Oxides (U,Pu)O2)C753 Specification for Nuclear-Grade, Sinterable Uranium Dioxide PowderC757 Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water ReactorsC859 Terminology Relating to Nuclear MaterialsC1233 Practice for Determining Equivalent Boron Contents o
17、f Nuclear MaterialsE105 Practice for Probability Sampling of MaterialsE112 Test Methods for Determining Average Grain Size2.2 ANSIASME Standard:3ANSI/ASMEASME NQA-1 Quality Assurance Requirements for Nuclear Facility Applications2.3 U.S. Government Documents:4USNRC Regulatory Guide 1.126 An Acceptab
18、le Model and Related Statistical Methods for the Analysis of Fuel DensificationCode of Federal Regulations Title 10, Part 50 Domestic Licensing of Production and Utilization FacilitiesCode of Federal Regulations Title 10, Part 71 Packaging and Transportation of Radioactive MaterialCode of Federal Re
19、gulations Title 49, Part 173 General Requirements for Shipments and Packaging3. Terminology3.1 DefinitionsDefinitions shall be in accordance withof terms are as given in Terminologies B243 Terminologyand C859.4. Technical Requirements4.1 Chemical RequirementsAll chemical analyses shall be performed
20、on portions of the representative sample prepared inaccordance with Section 6. Analytical chemistry methods shall be as stated in Test Methods C698 (latest edition) or demonstratedequivalent as mutually agreed to between the buyer and the seller.4.1.1 Uranium and Plutonium ContentUnless agreed upon
21、by the buyer and seller, individual powders shall meet therequirements of Specifications C753 and C757. The uraniumU and plutoniumPu contents combined shall be a minimum of 87.7 %weight 87.7 wt% on a dry weight basis compensated for the Am-241 Americium 241 (241Am) content. (Dry weight is defined as
22、the sample weight minus the moisture content). The plutonium content shall be that specified by the buyer, up to the limits coveredin this specification (15 %). (that is, 15 wt%).4.1.2 Impurity ContentThe impurity content shall not exceed the individual element limit specified in Table 1 based on th
23、eheavy metal content (uranium plus plutonium). (U + Pu +Am).The summation of the contribution of each of the impurity elementslisted in Table 1 shall not exceed 1500 g/g (U + Pu). Pu + Am). Some other elements such as those listed in Table 2 may alsobe of concern for the buyer and should be measured
24、 and reported if requested. If an element analysis is reported as “less than”a given concentration, this “less than” value shall be used in the determination of total impurities. Impurity elements measured andtheir associated limits may differ from what is listed in this specification as agreed upon
25、 between the buyer and seller.NOTE 1Higher impurity limits should be acceptable for restricted burnups and linear power ratings if there is evidence to substantiate the relaxation.Higher impurity levels of 450 ppm aluminum, 250 ppm carbon, 250 ppm nitrogen, and 450 ppm silicon have been supported fo
26、r burnups of less than35 000 MWd/t. The extension of the burnup limit may be determined by agreement between the buyer and seller as supporting data are accumulated.4.1.3 StoichiometryThe oxygen-to-heavy metal ratio (O/(U + Pu +Am) of sintered fuel pellets shall be within the range from1.98 to 2.02.
27、 The nominal value and allowable tolerance shall be agreed upon between the buyer and seller.4.1.4 Moisture ContentThe moisture content limit is included 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 P
28、ressure (0C bedetermined as agreed upon between the buyer and the seller. Typical methods include calculation based on C, N2, and oneH2atmosphere), 0.05 L/kg of the heavy metal content.contents or determination by high temperature vacuum extraction, orcombinations thereof.4.1.6 Americium-241 Content
29、The 241americium-241Am content shall be measured by the seller and reported to the buyer. The241americium-241Am content or activity is important in the handling of UO(U, Pu)O2-PuO2 pellets and subsequent heliumgeneration from alpha decay during irradiation and will vary with time. The maximum accept
30、able 241americium-241Am content2 For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at serviceastm.org. For Annual Book of ASTM Standardsvolume information, refer to the standards Document Summary page on the ASTM website.3 Available from American Nati
31、onal Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, Society of Mechanical Engineers (ASME), ASME International Headquarters,Two Park Ave., New York, NY 10036, http:/www.ansi.org.10016-5990, http:/www.asme.org.4 Available from U.S. Government Printing Office Superintendent of Documents, 732 N
32、. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http:/www.access.gpo.gov.http:/www.gpo.gov.C833 172on a given date along with the date of analysis shall be agreed upon between the buyer and seller. The dates of separation ofplutonium from this isotope and the analysis dates shall be conside
33、red;reported; methods of reporting shall be agreed upon betweenthe buyer and seller.4.2 Nuclear Requirements:TABLE 2 Isotopic RequirementsCharacteristic Grade R Grade F Grade N1Grade N2240Pu content, g 240Pu/g (Pu+Am) $ 0.19 $ 0.07 and 0.19 0.07 . . .240Pu/239Pu, g 240Pu/g 239Pu . . . . . . . . . #
34、0.10TABLE 2 Additional Impurity ElementsElementBeryllium (Be) Silver (Ag)Bismuth (Bi) Sodium (Na)Copper (Cu) Sulfur (S)Indium (In) Tantalum (Ta)Lead (Pb) Thorium (Th)Lithium (Li) Tin (Sn)Manganese (Mn) Titanium (Ti)Molybdenum (Mo) Tungsten (W)Neptunium (Np) Vanadium (V)Niobium (Nb) Zinc (Zn)Phosphor
35、ous (P) Zirconium (Zr)Potassium (K)TABLE 1 Impurity Elements and Maximum Concentration LimitsElement Maximum ConcentrationLimit (g/g of U + Pu)Aluminum 250Carbon 100Calcium + magnesium 200Chlorine 25Chromium 250Cobalt 100Fluorine 25Hydrogen (total from allsources)1.3Iron 500Nickel 250Nitride/nitroge
36、n 75Silicon 250TABLE 1 Impurity Elements and Maximum Concentration LimitsAElementBMaximum ConcentrationLimit (g/g of U + Pu +Am)Aluminum (Al) 250Carbon (C) 100Calcium (Ca)+ magnesium (Mg)200Chlorine (Cl) 25Chromium (Cr) 250Cobalt (Co) 100Fluorine (F) 25Hydrogen (H, total fromall sources)1.3Iron (Fe)
37、 500Nickel (Ni) 250Nitrogen (N) 75Silicon (Si) 250AHigher impurity limits should be acceptable for restricted burnups and linearpower ratings if there is evidence to substantiate the relaxation. Higher impuritylevels of 450 ppm aluminum, 250 ppm carbon, 250 ppm nitrogen, and 450 ppmsilicon have been
38、 supported for burnups of less than 35 000 MWd/t.The extensionof the burnup limit may be determined by agreement between the buyer and selleras supporting data are accumulated.BAny additional potential impurities, added by the fabrication process for example,beyond those listed here shall be evaluat
39、ed (for example, in terms of equivalentboron) and associated limits established and agreed upon between the buyer andseller.C833 1734.2.1 Isotopic ContentThe isotopic composition shall comply with the requirements of Table 2. The isotopic content of theamericium, uranium, U and plutoniumPu in the (u
40、ranium-plutonium) dioxide(U, Pu)O2 pellets shall be determined and the dateof the determination recorded. The 234U, 235U, 236U, and 238U content of the uranium shall be reported as a mass percentage withrespect to total uranium, on a U basis, and the 238Pu, 239Pu,240Pu, 241Pu, 242andPu, 242Puand 241
41、Am content of the plutoniumPushall be reported on a Pu mass % or on (Pu + Am) mass % or Pu + Am basis. The equivalent plutoniumPu content based onuraniumU and plutoniumPu isotopic concentrations shall be as agreed upon between the buyer and seller.4.2.2 Plutonium Equivalent at a Given Date(uranium-p
42、lutonium) dioxide(U, Pu)O2 fuel shall be considered as defined by theplutoniumPu content with adjustment (credit or debit) for the actual isotopic composition of plutonium, americium, Pu anduranium.Am. The dates of isotopic analyses in support of these determinations shall be recorded by the seller
43、and reported to thebuyer. The allowable tolerances of the plutoniumPu equivalent content (either as uranium plus plutoniumPu + Am or as theindividual elements) shall be as agreed upon between the buyer and seller.4.2.3 Equivalent Boron ContentFor thermal light water reactor use, the total equivalent
44、 boron content (EBC) shall not exceed4.0 g/g on a heavy metal basis. basis (g/g of (U + Pu + Am). The method of performing the calculation shall be as indicatedin Practice C1233. For the purposes of EBC calculation, B, Gd, Eu, Dy, Sm, and Cd shall be included.4.2.4 ReactivityAn integral test of reac
45、tivity may be performed and correlated to total EBC by a method agreed upon betweenthe buyer and the seller. If this is done, a total EBC need not be determined.4.3 Physical Characteristics:4.3.1 DimensionsThe dimensions of the pellet and their tolerances shall be specified by the buyer. These shall
46、 includediameter, length, perpendicularity, and, as required, other geometric parameters including surface finish.agreed upon between thebuyer and seller, other parameters including end-face configuration and surface finish. The diameter can be determined by three(3) multiple-point measurements at a
47、 minimum: middle and the two extremities of the pellet. Length measurements shall be madebetween the furthest extremities of the pellet on the land area.4.3.2 Pellet DensityThe density and tolerance of sintered pellets shall be as specified by the buyer. The theoretical density(TD) for UO2 shall be
48、considered to be 10.96 g/cm3. The theoretical density TD for PuO2 shall be considered to be 11.46 g/cm3.The theoretical densityAfter confirming the pellets are stoichiometric per 4.1.3, the TD for the (U, Pu)O2 pellets shall be calculatedby linear interpolation between these values. values based on
49、the Pu content. Density measurements shall be made by the methodstated in Specification C753 (for the geometric method), by an immersion density technique, or by demonstrated equivalent methodas mutually agreed upon between the buyer and the seller.seller, or combinations thereof.4.3.3 Grain Size and Pore MorphologySize DistributionBecause there is no unique structure for ensuring satisfactoryperformance, the pellet grain size and pore morphology size distribution shall be mutually agreed upon between the buyer and theseller. The mean
