1、Designation:C 1008 99(Reapproved 2008)Standard Specification forSintered(Uranium-Plutonium)DioxidePelletsFast Reactor Fuel1This standard is issued under the fixed designation C 1008;the number immediately following the designation indicates the year oforiginal adoption or,in the case of revision,the
2、 year of last revision.A number in parentheses indicates the year of last reapproval.Asuperscript epsilon(e)indicates an editorial change since the last revision or reapproval.INTRODUCTIONThis specification is intended to provide the nuclear industry with a general standard for(uranium-plutonium)dio
3、xide pellets for fast reactor use.It recognizes the diversity of manufacturingmethods by which(uranium-plutonium)dioxide pellets are produced and the many specialrequirements for chemical and physical characterization which may be imposed by the operatingconditions to which the pellets will be subje
4、cted in specific reactor systems.It does not recognize thepossible problems associated with the reprocessing of such pellets.It is therefore anticipated that thebuyer may supplement this specification with additional requirements for specific applications.1.Scope1.1 This specification is for finishe
5、d sintered(uranium-plutonium)dioxide pellets.It applies to(uranium-plutonium)dioxide pellets containing plutonium additions in the rangefrom 10 to 40 weight%and uranium of any235U content.Theisotopic composition of the plutonium component will be asnormally produced by in-reactor neutron irradiation
6、 of uraniumhaving less than 5%235U or by in-reactor neutron irradiationof recycled plutonium mixed with uranium.1.2 This specification does not include(1)provisions forpreventing criticality accidents or(2)requirements for healthand safety.Observance of this specification does not relieve theuser of
7、 the obligation to be aware of and conform to allapplicable international,federal,state,and local regulationspertaining to possessing,processing,shipping,or using sourceor special nuclear material.Examples of U.S.governmentdocuments are Code of Federal Regulations Title 10,Part 50 Domestic Licensing
8、 of Production and Utilization Facilities;Title 10,Part 71 Packaging and Transportation of Radioac-tive Material;and Title 49,Part 173 General Requirementsfor Shipments and Packaging.1.3 The following safety hazards caveat pertains only to thetechnical requirements portion,Section 4,of this specific
9、ation:This standard does not purport to address all of the safetyconcerns,if any,associated with its use.It is the responsibilityof the user of this standard to establish appropriate safety andhealth practices and determine the applicability of regulatorylimitations prior to use.2.Referenced Documen
10、ts2.1 ASTM Standards:2C 698 Test Methods for Chemical,Mass Spectrometric,andSpectrochemicalAnalysis of Nuclear-Grade Mixed Oxides(U,Pu)O2)C 753 Specification for Nuclear-Grade,Sinterable UraniumDioxide PowderC 757 Specification for Nuclear-Grade Plutonium DioxidePowder,SinterableC 859 Terminology Re
11、lating to Nuclear Materials3C 1165 Test Method for Determining Plutonium byControlled-Potential Coulometry in H2SO4at a PlatinumWorking ElectrodeC 1204 Test Method for Uranium in the Presence of Pluto-nium by Iron(II)Reduction in Phosphoric Acid Followedby Chromium(VI)TitrationC 1206 Test Method for
12、 Plutonium by Iron(II)/Chromium(VI)Amperometric TitrationE 105 Practice for Probability Sampling Of Materials2.2ANSI Standard:4ANSI/ASME NQA-1 Quality Assurance Program Require-ments for Nuclear Facility Applications1This specification is under the jurisdiction of ASTM Committee C26 onNuclear Fuel C
13、ycle and is the direct responsibility of Subcommittee C26.02 on Fueland Fertile Material Specifications.Current edition approved Jan.1,2008.Published February 2008.Originallyapproved in 1984.Last previous edition approved in 1999 as C 1008 99.2For referenced ASTM standards,visit the ASTM website,www
14、.astm.org,orcontact ASTM Customer Service at serviceastm.org.For Annual Book of ASTMStandards volume information,refer to the standards Document Summary page onthe ASTM website.3Withdrawn.4Available from American National Standards Institute(ANSI),25 W.43rd St.,4th Floor,New York,NY 10036,http:/www.
15、ansi.org.1Copyright ASTM International,100 Barr Harbor Drive,PO Box C700,West Conshohocken,PA 19428-2959,United States.Copyright by ASTM Intl(all rights reserved);Thu Apr 16 08:18:42 EDT 2009Downloaded/printed byLaurentian University pursuant to License Agreement.No further reproductions authorized.
16、2.3U.S.Government Documents:5Code of Federal Regulations,Title 10,(Energy)Part 50,Domestic Licensing of Production and Utilization Facili-ties(10 CFR 50)U.S.Department of Transportation,Title 49,Transportation,Chapter 1,Materials Transportation Bureau,applicableparts5U.S.Nuclear Regulatory Commission,Title 10,Part71,Packaging and Transportation of Radioactive Mate-rial53.Terminology3.1 DefinitionsDefinitions shall be in accordance withTerminology C 859.4.Technical Requirements4.1 Chemical Requir
