ASTM C1347-2008 Standard Practice for Preparation and Dissolution of Uranium Materials for Analysis《分析用铀材料制备和溶解的标准实施规程》.pdf
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1、Designation: C 1347 08Standard Practice forPreparation and Dissolution of Uranium Materials forAnalysis1This standard is issued under the fixed designation C 1347; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of last re
2、vision. 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 practice covers dissolution treatments for uraniummaterials that are applicable to the test methods used forcharacterizi
3、ng these materials for uranium elemental, isotopic,and impurities determinations. Dissolution treatments for themajor uranium materials assayed for uranium or analyzed forother components are listed.1.2 The treatments, in order of presentation, are as follows:Procedure Title SectionDissolution of Ur
4、anium Metal and Oxide with Nitric Acid 8.1Dissolution of Uranium Oxides with Nitric Acid and ResidueTreatment8.2Dissolution of Uranium-Aluminum Alloys in Hydrochloric Acidwith Residue Treatment8.3Dissolution of Uranium Scrap and Ash by Leaching with NitricAcid and Treatment of Residue by Carbonate F
5、usion8.4Dissolution of Refractory Uranium-Containing Material byCarbonate Fusion8.5Dissolution of UraniumAluminum AlloysUranium Scrap and Ash, and RefractoryUranium-Containing Materials byMicrowave Treatment8.61.3 The values stated in SI units are to be regarded asstandard. No other units of measure
6、ment are included in thisstandard.1.4 This standard does not purport to address all of thesafety concerns, if any, associated with its use. It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory limita
7、tions prior to use. Specific hazardsstatements are given in Section 7.2. Referenced Documents2.1 ASTM Standards:2C 753 Specification for Nuclear-Grade, Sinterable UraniumDioxide PowderC 776 Specification for Sintered Uranium Dioxide PelletsC 1168 Practice for Preparation and Dissolution of Pluto-niu
8、m Materials for AnalysisD 1193 Specification for Reagent Water3. Summary of Practice3.1 Many uranium-containing materials such as high-puritymetals and oxides dissolve readily in various mineral acids.The dissolution of uranium-plutonium mixed oxides is coveredin Practice C 1168. Highly refractory m
9、aterials require priorgrinding of samples and fusions to affect even partial dissolu-tion. Combinations of the mineral acid and fusion techniquesare used for difficult to dissolve materials.3,4,5Alternatively, thecombination of acids and a high pressure microwave have beenfound to be effective with
10、more difficult to dissolve materialsand can also be used for materials which dissolve in mineralacid in place of heating with a steam bath or hot plate.3.2 The dissolved materials are quantitatively transferred totared polyethylene bottles for subsequent sample solution massdetermination and factor
11、calculation. Aliquants are obtained bymass for high-precision analysis or by volume for less preciseanalysis methods. Quantitative transfers of samples and sub-sequent solutions are required. The sample is rejected when-ever a loss is incurred, or even suspected.3.3 Solutions of dissolved samples ar
12、e inspected for undis-solved particles. Further treatment is necessary to attain com-plete solubility if particles are present. When analyzing thedissolved sample for trace impurities, caution should beexercised so the dissolution process does not cause the impu-rity to be lost or does not increase
13、the level of impurity beingdetermined significantly.NOTE 1The use of double distilled acids may be necessary for lowlevel trace impurities. The use of plastic labware will be necessary so thedissolution does not increase the level of impurities being determined.This may be necessary in Section 8.6.3
14、.4 These dissolution procedures are written for the com-plete or nearly complete dissolution of samples to obtain1This practice is under the jurisdiction of ASTM Committee C26 on NuclearFuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods ofTest.Current edition approved Dec.
15、 1, 2008. Published December 2008. Originallyapproved in 1996. Last previous edition approved in 2002 as C 1347 02.2For 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 t
16、he standards Document Summary page onthe ASTM website.3Selected Measurement Methods for Plutonium and Uranium in the NuclearFuel Cycle, Second Edition, C. J. Rodden, ed., U.S. Atomic Energy Commission,1972.4Analysis of Essential Nuclear Reactor Materials, C. J. Rodden, ed., U.S.Atomic Energy Commiss
17、ion, 1964.5Larsen, R. P., “Dissolution of Uranium Metal and Its Alloys,” AnalyticalChemistry , Vol 31, No. 4, 1959, pp. 545549.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.destructive assay results on as near to 100 % of the sampl
18、e aspossible. When sample inhomogeneity is determined to be amajor contributor to assay error, nondestructive assay (NDA)determinations on residues from the dissolution may be re-quested at an earlier stage than suggested in these procedures;the contribution of the error to the total assay may bepro
19、pagated using the NDA assay value and errors for theresidue, and it may be determined that the error contributed tothe sample assay by the NDA determination on the residue isacceptable.3.5 The accuracy of the analytical method should be con-sidered when determining if complete dissolution of the sam
20、pleis required for difficult to dissolve matrices.4. Significance and Use4.1 The materials covered that must meet ASTM specifica-tions are uranium metal and uranium oxide.4.2 Uranium materials are used as nuclear reactor fuel. Forthis use, these materials must meet certain criteria for uraniumconten
21、t, uranium-235 enrichment, and impurity content, asdescribed in Specifications C 753 and C 776. The material isassayed for uranium to determine whether the content is asspecified.4.3 Uranium alloys, refractory uranium materials, and ura-nium containing scrap and ash are unique uranium materialsfor w
22、hich the user must determine the applicability of thispractice. In general, these unique uranium materials are dis-solved with various acid mixtures or by fusion with variousfluxes.5. Apparatus5.1 Balances, for determining the mass of samples andsolutions.5.2 Sample Mixing EquipmentSample tumbler or
23、 mixer,as appropriate; riffle splitter, stainless steel.5.3 FurnaceMuffle furnace, with fused silica tray to holdcrucibles, capable of operation to 1200C.5.4 Heating EquipmentAsteam bath in a hood; hot plates;infrared lamps; Bunsen and blast burner, with provision forboth gas and compressed air supp
24、ly; microwave oven6andhigh-pressure, heavy duty dissolution vessels.5.5 HardwareMetal weighing scoop; funnel racks; tongs;rubber policemen; tripods; silica triangles; board, heat dissi-pating, at least 6.35-mm (0.25-in.) thick.5.6 Beakers, Volumetric Flasks, and BottlesBorosilicateglass is generally
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