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本文(ASTM C1334-2005(2010) Standard Specification for Uranium Oxides with a 235U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide《转换成核纯级二氧化铀.pdf)为本站会员(fatcommittee260)主动上传,麦多课文库仅提供信息存储空间,仅对用户上传内容的表现方式做保护处理,对上载内容本身不做任何修改或编辑。 若此文所含内容侵犯了您的版权或隐私,请立即通知麦多课文库(发送邮件至master@mydoc123.com或直接QQ联系客服),我们立即给予删除!

ASTM C1334-2005(2010) Standard Specification for Uranium Oxides with a 235U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide《转换成核纯级二氧化铀.pdf

1、Designation: C1334 05 (Reapproved 2010)Standard Specification forUranium Oxides with a235U Content of Less Than 5 % forDissolution Prior to Conversion to Nuclear-Grade UraniumDioxide1This standard is issued under the fixed designation C1334; the number immediately following the designation indicates

2、 the year oforiginal adoption or, in the case of revision, 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 uranium oxides, inclu

3、dingprocessed byproducts or scrap material (powder, pellets, orpieces), that are intended for dissolution into uranyl nitratesolution meeting the requirements of Specification C788 priorto conversion into nuclear grade UO2powder with a235Ucontent of less than 5 %. This specification defines the impu

4、rityand uranium isotope limits for such urania powders that are tobe dissolved prior to processing to nuclear grade UO2asdefined in Specification C753.1.2 This specification provides the nuclear industry with ageneral standard for such uranium oxide powders. It recognizesthe diversity of conversion

5、processes and the processes towhich such powders are subsequently to be subjected (forinstance, by solvent extraction). It is therefore anticipated thatit may be necessary to include supplementary specificationlimits by agreement between the buyer and seller.1.3 The scope of this specification does

6、not comprehen-sively cover all provisions for preventing criticality accidents,for health and safety, or for shipping. Observance of thisspecification does not relieve the user of the obligation toconform to all international, national, state and local regula-tions for processing, shipping, or any o

7、ther way of using uraniapowders (see 2.2 and 2.3).2. Referenced Documents2.1 ASTM Standards:2C696 Test Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear-Grade Uranium Di-oxide Powders and PelletsC753 Specification for Nuclear-Grade, Sinterable UraniumDioxide PowderC788

8、 Specification for Nuclear-Grade Uranyl Nitrate Solu-tion or CrystalsC799 Test Methods for Chemical, Mass Spectrometric,Spectrochemical, Nuclear, and Radiochemical Analysis ofNuclear-Grade Uranyl Nitrate SolutionsC859 Terminology Relating to Nuclear MaterialsC996 Specification for Uranium Hexafluori

9、de Enriched toLess Than 5 %235UC1233 Practice for Determining Equivalent Boron Contentsof Nuclear MaterialsE105 Practice for Probability Sampling of Materials,2.2 ANSI Standard:3ANSI/ASME NQA-1 Quality Assurance Requirements forNuclear Facility Applications2.3 U.S. Government Document:4Federal Regul

10、ations Title 10, (Energy) Part 50, DomesticLicensing of Production and Utilization Facilities3. Terminology3.1 Definitions of Terms Specific to This Standard:3.1.1 Terms shall be defined in accordance with Terminol-ogy C859, except for the following:3.1.2 Commercial Grade Uranium Oxide, nany oxide o

11、furanium made from unirradiated uranium. It is recognizedsome contamination with reprocessed uranium may occurduring routine processing; this is acceptable provided that thespecification for Commercial Grade Uranium Oxide as setforth in 4.1 is met.3.1.3 scrap, nin the nuclear industry, residues that

12、 containsufficient quantities of source or special nuclear material to beworthy of recovery.4. Isotopic Content4.1 For Commercial Grade Uranium Oxide with an isotopiccontent of235U between that of natural uranium and 5 %, theisotopic and radionuclide limits of Specification C996 shall1This specifica

13、tion 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 March 1, 2010. Published April 2010. Originallyapproved in 1996. Last previous edition approved in 200

14、5 as C1334 051. DOI:10.1520/C1334-05R10.2For 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 Ameri

15、can National Standards Institute (ANSI), 25 W. 43rd St.,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.1Copyright ASTM International,

16、100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.apply. The specific isotopic and radionuclide measurementsrequired by Specification C996 may be waived, provided thatthe seller can demonstrate compliance through, for instance,the sellers quality assurance records.4

17、.2 For commercial uranium oxides not having an assay inthe range set forth in 4.1, the isotopic requirements shall be asagreed upon between the buyer and seller.5. Physical and Chemical Requirements5.1 Uranium ContentThe uranium content shall be deter-mined using methods described in Test Methods C6

18、96 andC799, or as agreed upon between the buyer and seller. Basedon the oxygen-to-uranium ratio, the minimum total uraniumcontent shall also be agreed upon between the buyer and seller.5.2 Impurity ContentThe impurity content shall not ex-ceed the individual element limits specified in Table 1. Thes

19、ummation of the contribution of each of the impurity elementslisted in Table 1 shall not exceed 1000 g/gU. The impuritycontent shall be determined using methods described in TestMethods C696 or as agreed upon between the buyer and seller.If the Table 1 specifications are not met, and processing beyo

20、ndsimple dissolution is anticipated, the concentrations of carbonand toxic elements such asAg, Cr, Pb, Hg, Se, Sb, andAs shallbe reported for information. Analysis requirements may bewaived provided the seller can characterize the material, forexample, through the sellers QA records.5.3 Equivalent B

21、oron ContentThe total equivalent boroncontent (EBC) shall not exceed 2.0 g/gU. The list of elementsto be considered in the EBC calculation shall be as recom-mended in Practice C1233. The method of performing thecalculation shall be as indicated in Practice C1233.5.4 If the concentrations of any of t

22、he elements used in thecalculations in 5.2 are reported as a less-than value, thisless-than value shall be used for any further calculationsinvolving the concentration of this element.5.5 Moisture ContentThe moisture content of the uraniumoxide shall not exceed 1 % by weight unless otherwise agreedu

23、pon by the buyer and seller.5.6 Ability to FlowThe Commercial Grade Uranium Ox-ide shall be sufficiently free-flowing to permit sampling andpowder handling.5.7 Particle SizeParticle size, size distribution andmethod of determination shall be as agreed upon between thebuyer and seller. Packing or agg

24、lomeration during shipping, orboth, may be a concern.5.8 DissolvabilityAt the buyers request, a dissolvabilitytest shall be performed by a procedure and to a specification asmutually agreed upon between buyer and seller. The testparameters (such as time, temperature, nitric acid molarity) andcharact

25、eristics to be measured (such as dissolution rate, in-solubles, foam generation) shall be defined by agreementbetween the buyer and seller.6. Lot Requirements6.1 A lot is defined as a quantity of Commercial GradeUranium Oxide powder that is uniform in isotopic, chemical,and flowability characteristi

26、cs.6.2 The identity of a lot shall be retained throughout.6.3 A powder lot shall form the basis for defining samplingplans used to establish conformance to this specification.6.4 Sampling plans shall be mutually agreed upon by thebuyer and seller. A suggested sampling procedure is given inAppendix X

27、1.7. Testing and Certification7.1 The material shall be sampled as described in AppendixX1 and tested to ensure conformance of the powder to therequirements as agreed upon between the buyer and the seller.7.2 The seller, as above, shall provide to the buyer docu-ments certifying that the material me

28、ets all the requirements ofSections 4, 5, and 6.7.3 Lot AcceptanceAcceptance testing may be performedby the buyer on either the sample provided by the seller or ona sample taken at the buyers plant by sampling one or moreindividual containers with a thief. Practice E105 is referencedas a guide. Acce

29、ptance shall be on a lot basis and shall becontingent upon the material properties meeting the require-ments of Sections 4, 5, and 6.7.4 Referee MethodThe buyer and seller may agree to athird party as a referee in the event of a dispute in analyticalresults.8. Packaging and Marking8.1 Uranium oxide

30、powder shall be packaged in sealedcontainers to prevent loss of material and undue contaminationfrom air or to the container materials. The exact size andmethod of packaging shall be as agreed upon between thebuyer and seller.8.2 Each container shall bear, as a minimum, a label on thelid and side wi

31、th the following information:8.2.1 Sellers name,8.2.2 Material in container,8.2.3 Lot number,TABLE 1 Impurity Elements and Maximum Concentration LimitsElementMaximum ConcentrationLimit (g/gU)Aluminum 150Barium 5Bismuth 3Calcium and Magnesium 150Chlorine 100Chromium 100Cobalt 80Copper 100Fluorine 100

32、Iron 150Lead 40Manganese 50Molybdenum 200Nickel 80Phosphorus 100Silicon 200Sodium 20Tantalum 200Thorium 10Tin 50Titanium 50Tungsten 100Vanadium 10Zinc 20C1334 05 (2010)28.2.4 Uranium enrichment,8.2.5 Gross, tare, net oxide weights,8.2.6 Uranium weight,8.2.7 Purchase order number (or equivalent), and

33、8.2.8 Container()of().9. Quality Assurance9.1 Quality assurance requirements shall be as agreed uponbetween the buyer and seller when specified in the purchaseorder. Code of Federal Regulations Title 10, Part 50, AppendixB and NQA-1 are referenced as guides.10. Keywords10.1 nuclear fuel; uranium oxi

34、de; uranium oxide dissolutionAPPENDIX(Nonmandatory Information)X1. SAMPLINGX1.1 Uranium oxide may be hygroscopic and retain suffi-cient water after exposure to a moist atmosphere to causedetectable error. Sample, weigh, and handle the sample underconditions that will ensure that the sample is repres

35、entative ofthe lot.X1.2 Take a representative sample of powder from each lotfor the purpose of determining chemical properties.X1.3 A lot sample shall be of sufficient size to performquality assurance testing at the sellers plant, acceptancetesting at the buyers plant, and referee tests in the event

36、 theybecome necessary.X1.4 Package the lot sample for acceptance testing at thebuyers plant in a separate container, clearly identify by lotnumber, and ship with the lot. Clearly identify the refereesample and retain it at the manufacturers (if someone otherthan the seller) plant until the lot has b

37、een formally accepted bythe buyer.X1.5 Prepare the lot sample by blending and splitting thecontainer samplesX1.6 To obtain a container sample, take specimens with athief at random locations along a randomly chosen verticaltraverse through each container selected at random to besampled. Then blend th

38、e thief samples from the selectedcontainers and split down to the required size.X1.7 The number of containers so sampled shall be 5 +(n/10) where n is the total number of containers per lot roundedto the nearest decade. If there are five or fewer containers perlot, each container shall be so sampled

39、.X1.8 Alternatively, an auto-sampler can be used to obtainsamples during emptying or filling of the container.ASTM 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

40、 that determination of the validity of any such patent rights, and the riskof infringement 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 rea

41、pproved or withdrawn. Your comments are invited either for revision of this standard 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 yo

42、u feel that your comments have not received a fair hearing you shouldmake your views 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

43、 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/).C1334 05 (2010)3

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