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
《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》由会员分享,可在线阅读,更多相关《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(3页珍藏版)》请在麦多课文档分享上搜索。
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
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