ASTM C1462-2000(2013) Standard Specification for Uranium Metal Enriched to More than 15&x2009 % and Less Than 20&x2009 % 235U《大于15%且小于20%浓缩铀金属U-235的标准规格》.pdf

《ASTM C1462-2000(2013) Standard Specification for Uranium Metal Enriched to More than 15&x2009 % and Less Than 20&x2009 % 235U《大于15%且小于20%浓缩铀金属U-235的标准规格》.pdf》由会员分享，可在线阅读，更多相关《ASTM C1462-2000(2013) Standard Specification for Uranium Metal Enriched to More than 15&x2009 % and Less Than 20&x2009 % 235U《大于15%且小于20%浓缩铀金属U-235的标准规格》.pdf（3页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: C1462 00 (Reapproved 2013)Standard Specification forUranium Metal Enriched to More than 15 % and Less Than20 %235U1This standard is issued under the fixed designation C1462; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revisi

2、on, 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.1. Scope1.1 This specification covers nuclear grade uranium metalthat has either been processed through an enrichm

3、ent 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 enriched

4、 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 commerc

5、ial 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 conditions

6、.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, federal,s

7、tate, and local regulations for processing, shipping, or anyother way of using uranium metal (see, for example, C996regarding references).2. Referenced Documents2.1 ASTM Standards:2C696 Test Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear-Grade Uranium Di-oxide Powde

8、rs and PelletsC799 Test Methods for Chemical, Mass Spectrometric,Spectrochemical, Nuclear, and Radiochemical Analysis ofNuclear-Grade Uranyl Nitrate SolutionsC859 Terminology Relating to Nuclear MaterialsC996 Specification for Uranium Hexafluoride Enriched toLess Than 5 %235UC1233 Practice for Deter

9、mining Equivalent Boron Contentsof Nuclear MaterialsC1295 Test Method for Gamma Energy Emission fromFission Products in Uranium Hexafluoride and UranylNitrate SolutionC1347 Practice for Preparation and Dissolution of UraniumMaterials for Analysis2.2 ANSI Standard3ANSI-ASME NQA-1 Quality Assurance Pr

10、ogram Require-ments for Nuclear Facility Applications2.3 U.S. Government Documents4Code of Federal Regulations, Title 10, Part 50, (Appendix B)3. Terminology3.1 Definitions of Terms Specific to This Standard:3.1.1 Definitions of Terms Specific to This StandardTerms shall be defined in accordance wit

11、h Terminology C859,except for the following:3.1.2 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.

12、3 commercial natural uraniumany form of naturalunirradiated uranium (containing 0.711 + 0.004 g235U per 100g U).3.1.4 depleted uraniumany form of unirradiated uraniumwith a235U content less than commercial natural uranium.1This specification is under the jurisdiction of ASTM Committee C26 onNuclear

13、Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fueland Fertile Material Specifications.Current edition approved Jan. 1, 2013. Published January 2013. Originallyapproved in 2000. Last previous edition approved in 2008 as C1462 00 (2008).DOI: 10.1520/C1462-00R13.2For referenced

14、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 National Standards Institute (ANSI), 25 W. 43rd St.,

15、4th Floor, New York, NY 10036, http:/www.ansi.org.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.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA

16、 19428-2959. United States13.1.5 highly enriched uraniumany form of uranium hav-ing a235U content equal to or in excess of 20 %.3.1.6 recovered uraniumany form of uranium that hasbeen exposed in a neutron irradiation facility and either hasbeen subsequently chemically separated from the fission prod

17、-ucts and transuranic isotopes so generated, or may be used asis, due to low irradiation levels.3.1.6.1 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 contai

18、ned fissile material or may havebeen utilized in critical facilities. It is recognized that differentlimits would be necessary to accommodate different fuelhistories.3.1.7 For enriched uranium metal transactions, “buyer”usually represents the research reactor operator or the fuelfabricator, and “sel

19、ler” usually represents the supplier of theenriched uranium 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 MethodC1295 or equivalent. See Note 1.NOTE 1Depe

20、nding upon the requirements of the fabricator utilizingenriched 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,

21、the totalalpha activity from transuranium elements shall be 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 b

22、e supplied as spherical, cubical,cylindrical or broken pieces, 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 ox

23、idefilm is allowable.5.1.4 The following impurity elements 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

24、 Sodium Na 25Cobalt Co 10 Tin Sn 100Copper Cu 50 Vanadium 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

25、 content (EBC) shall not exceed 4.0g/gU. The list of elements 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 C1233. For fast reactoruse, the above limitation o

26、n total EBC does not apply.5.2 Isotopic Requirements:5.2.1 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 allowablev

27、ariation for235U shall be 6 0.20 weight percent absolute 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. Typi

28、cally, a lot shall not be greater than 10kg.6.2 All samples 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 (Practic

29、e C1347), or demonstrated equivalent shallbe used as mutually 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 C696 or C799), or demonstrated equivalent,shall be used as mutually agreed up

30、on between the buyer andseller.8. Packaging, Handling, 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.

31、1 Quality assurance requirements shall be agreed uponbetween 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; u

32、ranium metalC1462 00 (2013)2ASTM International takes 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 infr

33、ingement of such rights, are entirely their own responsibility.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 standa

34、rd or for additional standardsand should be addressed 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 vie

35、ws known to the ASTM Committee on Standards, at the address 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). Permission rights to photocopy the standard may also be secured from the ASTM website (www.astm.org/COPYRIGHT/).C1462 00 (2013)3