ASTM C1462-2000(2005) Standard Specification for Uranium Metal Enriched to More than 15% and Less Than 20%235 U《大于15%小于20%的U-235的浓缩铀金属的标准规范》.pdf

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1、Designation: C 1462 00 (Reapproved 2005)Standard Specification forUranium Metal Enriched to More than 15 % and Less Than20 %235U1This standard is issued under the fixed designation C 1462; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revi

2、sion, the year of last revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon (e) indicates an editorial change since the last revision or reapproval.1. Scope1.1 This specification covers nuclear grade uranium metalthat has either been processed through an enri

3、chment plant, orhas been produced by the blending of highly enriched uraniumwith other uranium, to obtain uranium of any235U concentra-tion below 20 % (and greater than 15 %) and that is intendedfor research reactor fuel fabrication. The scope of this speci-fication includes specifications for enric

4、hed uranium metalderived from commercial natural uranium, recovered uranium,or highly enriched uranium. Commercial natural uranium,recovered uranium and highly enriched uranium are defined inSection 3. The objectives of this specification are to define theimpurity and uranium isotope limits for comm

5、ercial gradeenriched uranium metal.1.2 This specification is intended to provide the nuclearindustry with a standard for enriched uranium metal which is tobe used in the production of research reactor fuel. In additionto this specification, the parties concerned may agree to otherappropriate conditi

6、ons.1.3 The scope of this specification does not comprehen-sively cover all provisions for preventing criticality accidentsor requirements for health and safety or for shipping. Obser-vance of this standard does not relieve the user of theobligation to conform to all applicable international, federa

7、l,state, and local regulations for processing, shipping, or anyother way of using uranium metal (see, for example, C 996regarding references).2. Referenced Documents2.1 ASTM Standards:2C 696 Test Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear-Grade Uranium Di-oxide

8、Powers and PelletsC 799 Test Methods for Chemical, Mass Spectrometric,Spectrochemical, Nuclear, and Radiochemical Analysis ofNuclear-Grade Uranyl Nitrate SolutionsC 859 Terminology Relating to Nuclear MaterialsC 996 Specification for Uranium Hexafluoride Enriched toless than 5 %235UC 1233 Practice f

9、or Determining the Equivalent BoronContent of Nuclear MaterialC 1295 Test Method for Gamma Energy Emission fromFission Products in Uranium Hexafluoride and UraniumSolutionsC 1347 Practice for Preparation and Dissolution of UraniumMaterials for Analysis2.2 ANSI StandardANSI-ASME NQA-1 Quality Assuran

10、ce Program Require-ments for Nuclear Facility Applications32.3 U.S. Government DocumentsCode of Federal Regulations, Title 10, Part 50, (AppendixB)43. Terminology3.1 Definitions of Terms Specific to This StandardTermsshall be defined in accordance with Terminology C 859, exceptfor the following:3.1.

11、1 commercial grade enriched uranium metaluraniummetal derived from commercial natural uranium, recovereduranium, or uranium obtained from the blending of highlyenriched uranium with commercial natural uranium, recovereduranium, or depleted uranium.3.1.2 commercial natural uraniumany form of naturalu

12、nirradiated uranium (containing 0.711 + 0.004 g235U per 100g U).3.1.3 depleted uraniumany form of unirradiated uraniumwith a235U content less than commercial natural uranium.3.1.4 highly enriched uraniumany form of uranium hav-ing a235U content equal to or in excess of 20 %.3.1.5 recovered uraniuman

13、y form of uranium that hasbeen exposed in a neutron irradiation facility and either hasbeen subsequently chemically separated from the fission prod-ucts and transuranic isotopes so generated, or may be used asis, due to low irradiation levels.1This specification is under the jurisdiction of ASTM Com

14、mittee C26 onNuclear fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fueland Fertile Material Specifications.Current edition approved June 1, 2005. Published December 2005. Originallyapproved in 2000. Last previous edition approved in 2000 as C 146200.2Annual Book of ASTM Stand

15、ards, Vol 12.01.3Available from the American National Standards Institute, 11 W. 42nd St, 13thFloor, New York, NY 10036.4Available from the Superintendent of Documents, U.S. Government PrintingOffice, Washington, DC 20402.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Consho

16、hocken, PA 19428-2959, United States.3.1.5.1 DiscussionThe requirements for recovered ura-nium are intended to be typical of reprocessed spent fuel fromresearch reactors that have achieved burn-up levels of up to50 % of the originally contained fissile material or may havebeen utilized in critical f

17、acilities. It is recognized that differentlimits would be necessary to accommodate different fuelhistories.3.1.6 For enriched uranium metal transactions, “buyer”usually represents the research reactor operator or the fuelfabricator, and “seller” usually represents the supplier of theenriched uranium

18、 metal.4. Health Physics Requirements4.1 For commercial grade enriched uranium metal, thegamma activity from fission products shall not exceed 600Bq/gU. The measurements are to be made by Test MethodC 1295 or equivalent. See Note 1.NOTE 1Depending upon the requirements of the fabricator utilizingenr

19、iched uranium metal, gamma activity from fission products as high as6,000 Bq/gU may be acceptable, due to the utilization of reprocessedenriched uranium in producing the enriched uranium metal.4.2 For commercial grade enriched uranium metal, the totalalpha activity from transuranium elements shall b

20、e less than250 Bq/gU.5. Chemical, Physical, and Isotopic Requirements5.1 Physical Requirements:5.1.1 The uranium content of commercial grade enricheduranium metal shall be greater than or equal to 99.85 weightpercent.5.1.2 The product shall be supplied as spherical, cubical,cylindrical or broken pie

21、ces, with dimensions of not more than40 mm or less than 10 mm. The mass of individual pieces shallbe between 130 and 300 g.5.1.3 The individual pieces of product shall be free of looseor excessive oxides or contaminants. A tightly adhering oxidefilm is allowable.5.1.4 The following impurity elements

22、 shall not exceedthese values:Element g/gU Element g/gUAluminum Al 150 Magnesium Mg 50Boron B 1 Manganese Mn 50Beryllium Be 10 Molybdenum Mo 100Carbon C 800 Nickel Ni 100Calcium Ca 100 Phosphorus P 100Cadmium Cd 1 Silicon Si 250Chromium Cr 50 Sodium Na 25Cobalt Co 10 Tin Sn 100Copper Cu 50 Vanadium

23、V 30Iron Fe 250 Tungsten W 100Lead Pb 10 Zirconium Zr 250Lithium Li 10Rare Earths (Dy, Eu, Gd, Sm) 3.0The sum of the impurity elements shall not exceed 1500g/gU.5.1.5 Equivalent Boron ContentFor research reactor use,the total equivalent boron content (EBC) shall not exceed 4.0g/gU. The list of eleme

24、nts to be considered for the EBCcalculation shall be agreed upon between the buyer and theseller. The method of performing the calculation and the EBCFactors shall be as indicated in Practice C 1233. For fastreactor use, the above limitation on total EBC does not apply.5.2 Isotopic Requirements:5.2.

25、1 The following limits for commercial grade enricheduranium metal shall not be exceeded:232U 0.002 g/gU234U 0.01 g/gU236U 0.04 g/gU5.2.2 Uranium isotopic concentrations shall be determinedand reported for232U,234U,235U, and236U. The allowablevariation for235U shall be 6 0.20 weight percent absolute

26、fromthe nominal235U assay.6. Sampling6.1 A representative sample of sufficient size to performtests prescribed shall be taken from each lot. The size of a lotshall be as agreed upon between seller and buyer and shall befrom a single melt. Typically, a lot shall not be greater than 10kg.6.2 All sampl

27、es shall be clearly identified including thesellers lot number.6.3 All containers used for a lot shall be positively identifiedas containing material from a particular lot.6.4 ASTM standard practice for preparation of uraniummaterials (Practice C 1347), or demonstrated equivalent shallbe used as mut

28、ually agreed upon between the buyer and seller.7. Test Methods for Chemical and Isotopic Analysis7.1 ASTM test methods for chemical and isotopic analysis(Test Methods C 696 or C 799), or demonstrated equivalent,shall be used as mutually agreed upon between the buyer andseller.8. Packaging, Handling,

29、 and Shipping8.1 Procedures for packaging, handling, and shipping com-mercial grade enriched uranium metal are as agreed betweenbuyer and seller and shall be in accordance with applicablenational or international procedures.9. Quality Assurance9.1 Quality assurance requirements shall be agreed uponb

30、etween the buyer and the seller when specified in the purchaseorder. Code of Federal Regulations, Title 10, Part 50 (Appen-dix B) and NQA-1 are referenced as guides.10. Keywords10.1 medium enriched uranium; nuclear fuel; research reac-tor fuel; uranium metalC 1462 00 (2005)2ASTM International takes

31、no position respecting the validity of any patent rights asserted in connection with any item mentionedin this 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 respo

32、nsibility.This standard is subject to revision at any time by the responsible technical committee and must be reviewed 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

33、 to ASTM International Headquarters. Your comments 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 a

34、ddress shown below.This standard is copyrighted 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).C 1462 00 (2005)3