ASTM C1267-2017 Standard Test Method for Uranium by Iron (II) Reduction in Phosphoric Acid Followed by Chromium (VI) Titration in the Presence of Vanadium《使用铁II在磷酸中还原后在有钒的情况下滴铬(VI).pdf
《ASTM C1267-2017 Standard Test Method for Uranium by Iron (II) Reduction in Phosphoric Acid Followed by Chromium (VI) Titration in the Presence of Vanadium《使用铁II在磷酸中还原后在有钒的情况下滴铬(VI).pdf》由会员分享,可在线阅读,更多相关《ASTM C1267-2017 Standard Test Method for Uranium by Iron (II) Reduction in Phosphoric Acid Followed by Chromium (VI) Titration in the Presence of Vanadium《使用铁II在磷酸中还原后在有钒的情况下滴铬(VI).pdf(13页珍藏版)》请在麦多课文档分享上搜索。
1、Designation: C1267 11C1267 17Standard Test Method forUranium by Iron (II) Reduction in Phosphoric Acid Followedby Chromium (VI) Titration in the Presence of Vanadium1This standard is issued under the fixed designation C1267; the number immediately following the designation indicates the year oforigi
2、nal 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 test method, commonly referred to as the Modified Davies an
3、d Gray technique, covers the titration of uranium inproduct, fuel, and scrap materials after the material is dissolved. The test method is versatile and has been ruggedness tested. Withappropriate sample preparation, this test method can give precise and unbiased uranium assays over a wide variety o
4、f material types(1, 2).2 Details of the titration procedure in the presence of plutonium with appropriate modifications are given in Test MethodC1204.1.2 Uranium levels titrated are usually 20 to 50 mg, but up to 200 mg uranium can be titrated using the reagent volumes statedin this test method.1.3
5、The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibilityof the user of this standard to establish appro
6、priate safety safety, health, and healthenvironmental practices and determine theapplicability of regulatory limitations prior to use. For specific safeguard and safety precaution statements, see Section 45.1.5 This international standard was developed in accordance with internationally recognized p
7、rinciples on standardizationestablished in the Decision on Principles for the Development of International Standards, Guides and Recommendations issuedby the World Trade Organization Technical Barriers to Trade (TBT) Committee.2. Referenced Documents2.1 ASTM Standards:3C696 Test Methods for Chemical
8、, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium DioxidePowders and PelletsC799 Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate SolutionsC859 Terminology Relating to Nuclear MaterialsC1068
9、Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear IndustryC1128 Guide for Preparation of Working Reference Materials for Use in Analysis of Nuclear Fuel Cycle MaterialsC1204 Test Method for Uranium in Presence of Plutonium by Iron(II) Reduction in Phosphoric Acid Foll
10、owed byChromium(VI) TitrationC1346 Practice for Dissolution of UF6 from P-10 TubesC1347 Practice for Preparation and Dissolution of Uranium Materials for Analysis2.2 NIST Standard:4SRM 136e Potassium Dichromate (Oxidimetric Standard)2.3 NBL Standard:5CRM 112A Uranium Metal Standard1 This test method
11、 is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of Test.Current edition approved June 1, 2011Nov. 1, 2017. Published June 2011November 2017. Originally approved in 1994. Last previous edition approved in 200620
12、11 asC1267 06.C1267 11. DOI: 10.1520/C1267-11.10.1520/C1267-17.2 The boldface numbers in parentheses refer to the list of references at the end of this standard.3 For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at serviceastm.org. For Annual Book of
13、 ASTM Standardsvolume information, refer to the standards Document Summary page on the ASTM website.4 Available from National Institute of Standards and Technology (NIST), 100 Bureau Dr., Stop 1070, Gaithersburg, MD 20899-1070, http:/www.nist.gov.5 New Brunswick Laboratory (NBL) Certified Reference
14、Materials Catalog (U.S. Department of Energy), http:/www.nbl.doe.gov.http:/science.energy.gov/nbl.This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Becauseit may not be technically
15、possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current versionof the standard as published by ASTM is to be considered the official document.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700
16、, West Conshohocken, PA 19428-2959. United States13. Terminology3.1 Except as otherwise defined herein, definitions of terms are as given in Terminology C859.4. Summary of Test Method4.1 Samples are prepared by dissolution techniques detailed in Practices C1346, C1347, or Refs (2), (3), and (4). App
17、ropriateuncertainties for sampling and weight determination should be applied to the overall precision and bias calculations for the finalresult.Aliquants containing 20 to 200 mg of uranium are prepared by weight. The sample is fumed to dryness after the appropriateacid treatment. The sample is diss
18、olved in dilute nitric acid or water prior to titration.4.2 Uranium is reduced to uranium(IV) by excess iron(II) in concentrated phosphoric acid (H3PO4) containing sulfamic acid.The excess iron(II) is selectively oxidized by nitric acid (HNO3) in the presence of a molybdenum(VI) catalyst. After the
19、additionof a vanadium(IV) solution, the uranium(IV) is titrated with chromium(VI) to a potentiometric end point.4.3 The chromium(VI) titrant may be delivered manually on a weight or on a volumetric basis as specified by the facilitytitration procedure.4.3.1 If the titrant is delivered on a volumetri
20、c basis, corrections to the volume of titrant may be needed to adjust for thedifference between the temperature of preparation and the ambient temperature.4.3.2 Automated titrators are facility specific and are not explicitly addressed in this test method. However, automated titratorswhich have comp
21、arable bias and precision may be used.4.3.3 There is an alternate, high precision (;0.005 % RSD) modified Davies and Gray titration, which is similar to the methodcovered in this procedure. In the high precision method, the amount of uranium titrated is increased and about 90 % of the titrantis deli
22、vered on a solid weight basis followed by titration to the end point with a dilute titrant. Details of this alternate method areavailable in Ref (5).5. Significance and Use5.1 Factors governing selection of a method for the determination of uranium include available quantity of sample, homogeneityof
23、 material sampled, sample purity, desired level of reliability, and facility available equipment.5.2 This uranium assay method is referenced in the Test Methods for Chemical, Mass Spectrometric, and SpectrochemicalAnalysis of Nuclear-Grade Uranium Dioxide Powders and Pellets (Test Methods C696) and
24、in the Test Methods for Chemical,Mass Spectrometric, and Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate Solutions (TestMethods C799). This uranium assay method may also be used for uranium hexafluoride and uranium ore concentrate. This testmethod determines 20 t
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