ASTM C753-2016a Standard Specification for Nuclear-Grade Sinterable Uranium Dioxide Powder《核级可烧结二氧化铀粉末的标准规格》.pdf
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1、Designation: C753 16C753 16aStandard Specification forNuclear-Grade, Sinterable Uranium Dioxide Powder1This standard is issued under the fixed designation C753; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of last revis
2、ion. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon () indicates an editorial change since the last revision or reapproval.INTRODUCTIONThis specification is intended to provide the nuclear industry with a general standard for sinterableuranium dioxide (UO2) powde
3、r. It recognizes the diversity of manufacturing methods by which UO2powders are produced and the many special requirements for chemical and physical characterizationthat may be applicable for a particular fuel pellet manufacturing process or imposed by the end userof the powder in a specific reactor
4、 system. It is, therefore, anticipated that the buyer may supplementthis specification with more stringent or additional requirements for specific applications.1. Scope1.1 This specification covers nuclear-grade, sinterable UO2 powder. It applies to UO2 powder containing uranium (U) ofany 235U conce
5、ntration in the production of nuclear fuel pellets for use in nuclear reactors.1.2 This specification recognizes the presence of reprocessed U in the fuel cycle and consequently defines isotopic limits forcommercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and m
6、anufacture, the product isessentially equivalent to that made from unreprocessed U. UO2 falling outside these limits cannot necessarily be regarded asequivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design.1.3 This specification does not include provisions
7、 for preventing criticality accidents or requirements for health and safety.Observance of this specification does not relieve the user of the obligation to be aware of and conform to all international, national,or federal, state, and local regulations pertaining to possessing, shipping, processing,
8、or using source or special nuclear material.1.4 This specification refers expressly to UO2 powder before the addition of any die lubricant, binder, or pore former. If powderis sold with such additions or prepared as press feed, sampling procedures, allowable impurity contents, or powder physicalrequ
9、irements may need to be modified by agreement between the buyer and the seller.1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.1.6 This standard does not purport to address all of the safety concerns, if any, associated w
10、ith its use. It is the responsibilityof the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatoryrequirements prior to use.2. Referenced Documents2.1 ASTM Standards:2B243 Terminology of Powder MetallurgyB329 Test Method for Apparent
11、Density of Metal Powders and Compounds Using the Scott VolumeterC696 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium DioxidePowders and PelletsC859 Terminology Relating to Nuclear MaterialsC996 Specification for Uranium Hexafluoride Enriched to Le
12、ss Than 5 % 235UC1233 Practice for Determining Equivalent Boron Contents of Nuclear MaterialsE11 Specification for Woven Wire Test Sieve Cloth and Test Sieves1 This specification is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C2
13、6.02 on Fuel and FertileMaterial Specifications.Current edition approved Feb. 1, 2016April 1, 2016. Published March 2016April 2016. Originally approved in 1973. Last previous edition approved in 20092016 asC753 04 (2009).C753 16. DOI: 10.1520/C0753-16.10.1520/C0753-16A.2 For referencedASTM standards
14、, visit theASTM website, www.astm.org, or contactASTM Customer Service at serviceastm.org. For Annual Book of 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 s
15、tandard an indication of what changes have been made to the previous version. Becauseit may not be technically 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
16、ASTM is to be considered the official document.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States1E105 Practice for Probability Sampling of Materials2.2 ASME Standard:3ASME NQA-1 Quality Assurance Requirements for Nuclear Facility Applic
17、ations2.3 Federal Regulation:4Code of Federal Regulations, Title 10, Chapter 1, Nuclear Regulatory Commission, Applicable Parts3. Terminology3.1 DefinitionsDefinitions of terms are as given in Terminologies B243 and C859.4. Chemical Composition4.1 Uranium ContentThe U content shall be determined on
18、a basis to be agreed upon between the buyer and seller.4.2 Oxygen-to-Uranium Ratio (O/U)The O/U ratio may be specified as agreed upon between the buyer and seller. Thedetermination of the O/U ratio shall be in accordance with Test Methods C696 or a demonstrated equivalent.4.3 Impurity ContentThe imp
19、urity content shall not exceed the individual element limit specified in Table 1 on a U basis.Totalnon-volatile oxide impurity content (see Table 1 and other impurity elements not having associated limits in Table 2) shall notexceed 1500 g/gU. Some other elements such as those listed in Table 2 may
20、also be of concern for the buyer and should bemeasured and reported if requested. If an element analysis is reported as “less than” a given concentration, this “less than” valueshall be used in the determination of total impurities. Impurity elements measured and their associated limits may differ f
21、rom whatis listed in this specification agreed upon between the buyer and seller.4.4 Moisture ContentThe moisture content shall not exceed 0.50 weight percent of the powder.4.5 Isotopic Content:4.5.1 For UO2 powder with an isotopic content of 235U below 5 %, the isotopic limits of Specification C996
22、 shall apply, unlessotherwise agreed upon between the buyer and the seller. If the 236U content is greater than Enriched Commercial Grade UF6requirements, the isotopic analysis requirements of Specification C996 shall apply. The specific isotopic measurements requiredby Specification C996 may be wai
23、ved, provided that the seller can demonstrate compliance with Specification C996, for instance,through the sellers quality assurance records.3 Available from American Society of Mechanical Engineers (ASME), ASME International Headquarters, Two Park Ave., New York, NY 10016-5990, http:/www.asme.org.4
24、 Available from U.S. Government Printing Office, Superintendent of Documents, 732 N. Capitol St., NW, Washington, DC 20401-0001, http:/www.access.gpo.gov.TABLE 1 Impurity Elements and Maximum Concentration LimitsElementB Maximum ConcentrationLimit of Uranium, g/gUAluminum (Al) 300Carbon (C) 100Calci
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