ASTM C1845-2016 Standard Practice for The Separation of Lanthanide Elements from Uranium Matrices Using High Pressure Ion Chromatography (HPIC) for Isotopic Analyses by Inductively.pdf
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1、Designation: C1845 16Standard Practice forThe Separation of Lanthanide Elements from UraniumMatrices Using High Pressure Ion Chromatography (HPIC)for Isotopic Analyses by Inductively Coupled Plasma MassSpectrometry (ICP-MS)1This standard is issued under the fixed designation C1845; the number immedi
2、ately following the designation indicates 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 p
3、ractice provides instructions for the rapid separa-tion of lanthanide elements using high pressure ion chroma-tography (HPIC) from dissolved uranium materials such as:nuclear fuels, uranium ores, hydrolyzed UF6, and depleted,natural, or enriched oxides/powders, or metals. Whenoptimized, this techniq
4、ue will produce purified elementalfractions of the lanthanide elements isolated from the bulkuranium matrix allowing for isotopic assay using inductivelycoupled plasma mass spectrometry (ICP-MS).1.2 This practice is most applicable for analyte concentra-tions of nanograms per gram uranium or higher.
5、 For ICP-MSdetection and measurement of analyte concentrations lowerthan this, it would be necessary to perform additional pre-cleanup or concentration techniques, or both, which are notaddressed in this practice.1.3 When combined with isotope dilution, this practice canalso be used for improved pre
6、cision assays of the lanthanideelements using the principle of isotope dilution mass spectrom-etry (IDMS).1.4 The values stated in SI units are to be regarded asstandard. No other units of measurement are included in thispractice.1.5 This standard does not purport to address all of thesafety concern
7、s, 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 limitations prior to use.2. Referenced Documents2.1 ASTM Standards:2C859 Terminology Relating to Nuclear Mater
8、ialsC1052 Practice for Bulk Sampling of Liquid UraniumHexafluorideC1075 Practices for Sampling Uranium-Ore ConcentrateC1168 Practice for Preparation and Dissolution of PlutoniumMaterials for AnalysisC1347 Practice for Preparation and Dissolution of UraniumMaterials for AnalysisC1689 Practice for Sub
9、sampling of Uranium HexafluorideC1769 Practice for Analysis of Spent Nuclear Fuel to De-termine Selected Isotopes and Estimate Fuel BurnupD1193 Specification for Reagent WaterE105 Practice for Probability Sampling of Materials3. Terminology3.1 DefinitionsFor definitions of terms used in thispractice
10、, refer to Terminology C859.4. Summary of Practice4.1 Solid samples are dissolved according to PracticesC1168, C1347, or other appropriate methods. Uraniumhexafluoride can be sampled in accordance with PracticesC1052 and C1689. The resulting dissolver solution is pro-cessed to produce solutions of i
11、solated lanthanide elements formass spectrometric isotopic analysis. The elements are selec-tively separated from the dissolver solution and collected usingHPIC instrumentation equipped with automated fraction col-lection. Appropriate aliquots of the unseparated dissolutions1This practice is under t
12、he jurisdiction of ASTM Committee C26 on NuclearFuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods ofTest.Current edition approved June 1, 2016. Published June 2016. DOI: 10.1520/C1845-16.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM
13、Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States1are taken to provide up to 100 n
14、g/mL of a lanthanide elementon the analytical column to be separated from 3.5 mg/mL orless of uranium. In a strong nitric acid matrix, no pre-separation valence adjustments are necessary.NOTE 1This practice has been verified to separate 0.7 mg of totaluranium from the lanthanide analytes. 20 ng tota
15、l of each analyte has beenshown to have efficient resolution on the column to yield purifiedelemental samples. If larger uranium and analytes sample sizes are beingconsidered, it is suggested that these be verified by the lab for efficienturanium removal and analyte resolution.4.2 For the separation
16、 HPIC sample aliquots are injectedusing a 200 L sample loop and loaded ontoa4by250mmhigh pressure cation exchange column with sulfonic acidfunctional groups and an ion exchange capacity of 80micro-equivalents/columns. First, complexation and removalof the bulk dissolved uranium matrix is accomplishe
17、d using adilute hydrochloric acid eluent which is directed to waste.Next, the lanthanide elements are selectively eluted off of thecolumn by chelation chromatography using a dilute solution of2-hydroxyisobutyric acid (-HIBA). Fractions are collected atautomated 20 s time intervals to allow for recov
18、ery of theseparated analytes, producing purified aliquots of each lan-thanide element from the bulk uranium matrix of the dissolversolution for isotopic measurements using ICP-MS.5. Significance and Use5.1 The measurement of isotopic distributions for the lan-thanide series elements is of important
19、to all phases of thenuclear fuels cycle. Examples include the purification of theNd isotopes from Ce and Sm isotopes for the determination ofatom percent fission through the production of148Nd inirradiated nuclear fuels using Practice C1769, determination ofrare earth content and isotopic distributi
20、on in Uranium OreConcentrates (UOC) for source term and production of lan-thanide fission products in irradiated nuclear fuels for determi-nation of performance, improvements of depletion codes, andanalysis of burnup indicators.36. Interferences6.1 High salt content in the sample can potentially inf
21、luenceboth the retention times and the resolution of the analytes. Theconcentration of the nitric acid in the sample matrix does notnecessarily influence the retention times and the resolution ofthe analytes, but it can influence the removal of uranium. 2 Mnitric acid has been successful in efficien
22、tly removing uranium.6.2 The presence of high concentrations of sulfate,phosphate, oxalate, and halides in the sample matrix willpotentially have an effect on the retention times and theresolution of the analytes.NOTE 2Using a smaller sample injection loop volume with a higheranalyte concentration c
23、an reduce the effects of the matrix on the retentiontimes and the resolution of the analytes.6.3 Temperature can impact the retention times and theresolution of the analytes and, where possible, a thermalcompartment should be employed to maintain consistencybetween sample analyses.7. Apparatus7.1 Hi
24、gh pressure ion chromatograph equipped with asingle variable speed gradient pump capable of delivering flowrates of 0.001 to 10 mL/min. The system requires eluent degascapability and a low pressure gradient mixer capable of mixingfour independent eluent streams.7.1.1 Optionally the HPIC may be equip
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