ASTM C1457-2018 Standard Test Method for Determination of Total Hydrogen Content of Uranium Oxide Powders and Pellets by Carrier Gas Extraction《用载气萃取法测定氧化铀粉末和丸粒总氢含量的标准试验方法》.pdf
《ASTM C1457-2018 Standard Test Method for Determination of Total Hydrogen Content of Uranium Oxide Powders and Pellets by Carrier Gas Extraction《用载气萃取法测定氧化铀粉末和丸粒总氢含量的标准试验方法》.pdf》由会员分享,可在线阅读,更多相关《ASTM C1457-2018 Standard Test Method for Determination of Total Hydrogen Content of Uranium Oxide Powders and Pellets by Carrier Gas Extraction《用载气萃取法测定氧化铀粉末和丸粒总氢含量的标准试验方法》.pdf(5页珍藏版)》请在麦多课文档分享上搜索。
1、Designation: C1457 00 (Reapproved 2010)1C1457 18Standard Test Method forDetermination of Total Hydrogen Content of Uranium OxidePowders and Pellets by Carrier Gas Extraction1This standard is issued under the fixed designation C1457; the number immediately following the designation indicates the year
2、 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 NOTEEditorial corrections were made throughout in June 2010.1. Sco
3、pe1.1 This test method applies to the determination of hydrogen in nuclear-grade uranium oxide powders and pellets to determinecompliance with specifications. Gadolinium oxide (Gd2O3) and gadolinium oxide-uranium oxide powders and pellets may also beanalyzed using this test method.1.2 This standard
4、describes a procedure for measuring the total hydrogen content of uranium oxides. The total hydrogen contentresults from absorbed water, water of crystallization, hydro-carbides and other hydrogenated compounds which may exist as fuelsimpurities.1.3 This test method covers the determination of 0.05
5、to 200 g of residual hydrogen.1.4 This test method describes an electrode furnace carrier gas combustion system equipped with a thermal conductivitydetector.1.5 The preferred system of units is micrograms hydrogen per gram of sample (g/g sample) or micrograms hydrogen per gramof uranium (g/g U).1.6
6、The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.1.7 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
7、priate safety safety, health, and healthenvironmental practices and determine theapplicability of regulatory limitations prior to use. For specific hazard statements, see Section 9.1.8 This international standard was developed in accordance with internationally recognized principles on standardizati
8、onestablished 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:2C753 Specification for Nuclear-Grade, Sinterable Uranium
9、 Dioxide PowderC776 Specification for Sintered Uranium Dioxide Pellets for Light Water ReactorsC859 Terminology Relating to Nuclear MaterialsC888 Specification for Nuclear-Grade Gadolinium Oxide (Gd2O3) PowderC922 Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets3. Terminology3.1 D
10、efinitions:3.1.1 For definitions of terms relating to the nuclear fuel cycle, refer to Terminology C859.4. Summary of Test Method4.1 The total hydrogen content is determined using a hydrogen analyzer. The hydrogen analyzer is based on the carrier gasmethod using argon or nitrogen as carrier gas. The
11、 actual configuration of the system may vary with vendor and model.1 This test method 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, 2010Feb. 1, 2018. Published June 201
12、0February 2018. Originally approved in 2000. Last previous edition approved in 20052010 asC1457 00 (2005).(2010)1. DOI: 10.1520/C1457-00R10E01.10.1520/C1457-18.2 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.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
14、 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 C70
15、0, West Conshohocken, PA 19428-2959. United States14.2 The samples to be analyzed are dropped into a preheated graphite crucible, and then, heated up to a temperature of morethan 1700C in a graphite crucible. At that temperature hydrogen, oxygen, nitrogen, and carbon monoxide (oxygen is convertedto
16、CO when it reacts with the crucible) are released. The release gas is purified in the carrier gas stream by oxidation and absorptioncolumns. The hydrogen is separated by chromatographic means and analyzed in a thermal conductivity detector.5. Significance and Use5.1 Uranium dioxide is used as a nucl
17、ear-reactor fuel. Gadolinium oxide is used as an additive to uranium dioxide. In order tobe suitable for this purpose, these materials must meet certain criteria for impurity content. This test method is designed todetermine whether the hydrogen content meets Specifications C753, C776, C888, and C92
18、2.6. Interferences6.1 Contamination of carrier gas, crucibles, or samples with extraneous sources of hydrogen may cause a positive bias.Ablankcorrection will help to minimize the bias from carrier gas and crucibles. Interference from adsorbed hydrogen on samples may beeliminated by keeping the sampl
19、e in an inert atmosphere or vacuum.6.2 The purification system typically associated with the recommended combustion and detection equipment is designed tominimize other expected sources of interferences, such as sulfur, halogens, carbon monoxide, carbon dioxide, and water.6.2.1 The nitrogen and hydr
20、ogen peaks are close together and must be well-separated to prevent falsely high result from thenitrogen. The molecular sieve must be sufficiently long to separate the peaks and must be changed when the column becomesloaded with contaminants that prevent proper peak separation.6.3 The temperature of
21、 17001800C must be reached. If not, the decomposition of the released water to hydrogen and carbonmonoxide may not be complete. The temperature will depend upon the instrument and type of graphite crucible used. Single wallcrucibles will require a lower temperature (power) than double wall crucibles
22、.6.4 Incomplete fusion may result in partial or a late release of hydrogen resulting in low results.6.5 At temperatures of more than 2200C uranium metal may be formed, and carbon dioxide released because of reduction ofUO2 by the graphite crucible.6.5.1 Carbon dioxide will interfere with the thermal
23、 conductivity measurement. This interference can be minimized by use ofchemical absorption, or a molecular sieve column, or both.6.5.2 Excess temperature, from too much power, crucible hot spots, or from misaligned electrodes may cause analysis errors.Uranium samples should be evenly fused, fall out
24、 freely of the crucibles and contain very little uranium metal.7. Apparatus7.1 Hydrogen Analyzer, consisting of an electrode furnace capable of operation at least up to 2200 to 2500C, a thermalconductivity detector for measuring, and auxiliary purification systems.7.2 Balance, with precision of 6 1
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