ASTM C1347-2002 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 02Standard 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 (e) 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 forcharacteriz
3、ing 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 U
4、ranium 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
5、Fusion8.4Dissolution 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 as thestandard. The values given in
6、parentheses are for informationonly.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 limi
7、tations prior to use. Specific hazardsstatements are given in Section 7.2. Referenced Documents2.1 ASTM Standards:C 753 Specification for Nuclear-Grade, Sinterable UraniumDioxide Powder2C 776 Specification for Sintered Uranium Dioxide Pellets2C 1168 Practice for Preparation and Dissolution of Pluto-
8、nium Materials for Analysis2D 1193 Specification for Reagent Water33. 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 refract
9、ory materials 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.4,5,6Alternatively, thecombination of acids and a high pressure microwave have beenfound to be effective
10、with 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 fa
11、ctor 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 sampl
12、es are 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 incr
13、ease the level of impurity beingdetermined significantly.3.4 These dissolution procedures are written for the com-plete or nearly complete dissolution of samples to obtaindestructive assay results on as near to 100 % of the sample aspossible. When sample inhomogeneity is determined to be amajor cont
14、ributor 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;1This practice is under the jurisdiction of ASTM Committee C26 on NuclearFuel Cycle and is the direct responsibility of Subcommit
15、tee C26.05 on Methods ofTest.Current edition approved August 10, 2002. Published November 2002. Origi-nally published as C 1347 96. Last previous edition C 1347 96a.2Annual Book of ASTM Standards, Vol 12.01.3Annual Book of ASTM Standards, Vol 11.01.4Selected Measurement Methods for Plutonium and Ura
16、nium in the NuclearFuel Cycle, Second Edition, C. J. Rodden, ed., U.S. Atomic Energy Commission,1972.5Analysis of Essential Nuclear Reactor Materials, C. J. Rodden, ed., U.S.Atomic Energy Commission, 1964.6Larsen, R. P., “Dissolution of Uranium Metal and Its Alloys,” AnalyticalChemistry, Vol 31, No.
17、 4, 1959, pp. 545549.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.the contribution of the error to the total assay may bepropagated using the NDA assay value and errors for theresidue, and it may be determined that the error contr
18、ibuted 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 sampleis required for difficult to dissolve matrices.4. Significance and Use4.1 The materials covered that mu
19、st 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 uraniumcontent, uranium-235 enrichment, and impurity content, asdescribed in Specifications C 753 and C 776. The materi
20、al 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 which the user must determine the applicability of thispractice. In general, these unique uranium materials
21、 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 mixer,as appropriate; riffle splitter, stainless steel.5.3 FurnaceMuffle furnace, with fused silica tray
22、to holdcrucibles, capable of operation to 1200C.5.4 Heating EquipmentA steam bath in a hood; hot plates;infrared lamps; Bunsen and blast burner, with provision forboth gas and compressed air supply; microwave oven7andhigh-pressure, heavy duty dissolution vessels.5.5 HardwareMetal weighing scoop; fun
23、nel 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 recommended. However, the analyst shouldbe sure that safety and sample contamination are consideredwhen
24、choosing appropriate containers.5.7 GlasswareBorosilicate glass is generally recom-mended except as specified. Watch glasses or petri dishes, tocover beakers; funnels; stirring rods; crucibles, Vycor, withlids.5.8 PlasticwareWash bottle, polyethylene, 125-mL, foraliquanting; petri dishes; narrow mou
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