1、Designation:C83317Standard Specification forSintered(Uranium-Plutonium)Dioxide Pellets for LightWater Reactors1This standard is issued under the fixed designation C833;the number immediately following the designation indicates the year oforiginal adoption or,in the case of revision,the year of last
2、revision.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 foruranium-plutonium dioxide(U,Pu)O2)pel
3、lets for light water reactor use.It recognizes the diversityof manufacturing methods by which(U,Pu)O2pellets are produced and the many special requirementsfor chemical and physical characterization that may be imposed by the operating conditions to whichthe pellets will be subjected in different lig
4、ht water reactors.It does not recognize the possibleproblems associated with the reprocessing of such pellets.It is,therefore,anticipated that thepurchaser may supplement this specification with additional requirements for specific applications.1.Scope1.1 This specification covers finished sintered
5、and ground(U,Pu)O2pellets for use in light water reactors.It applies to(U,Pu)O2pellets containing plutonium additions up to15 weight%(wt%;that is,0.15 g Pu/g(U+Pu+Am).1.2 Pellets produced under this specification are available infour grades.1.2.1 Grade R240Pu content of(Pu+Am)(that is,g240Pu/g(Pu+Am
6、)is at least 19%.1.2.2 Grade F240Pu content of(Pu+Am)is at least 7%and less than 19%.1.2.3 Grade N1240Pu content of(Pu+Am)is less than 7%.1.2.4 Grade N2240Pu/239Pu does not exceed 0.10.1.3 There is no discussion of or provision for preventingcriticality incidents,nor are health and safety requiremen
7、ts,theavoidance of hazards,or shipping precautions and controlsdiscussed.Observance of this specification does not relieve theuser of the obligation to be aware of and conform to allapplicable international,federal,state,and local regulationspertaining to possessing,processing,shipping,or using sour
8、ceor special nuclear material.Examples of U.S.governmentdocuments are Code of Federal Regulations Title 10,Part50Domestic Licensing of Production and Utilization Facili-ties;Code of Federal Regulations Title 10,Part 71Packagingand Transportation of Radioactive Material;and Code ofFederal Regulations
9、 Title 49,Part 173General Requirementsfor Shipments and Packaging.1.4 The values stated in SI units are to be regarded asstandard.No other units of measurement are included in thisstandard.1.5 The following safety hazards caveat pertains only to thetechnical requirements portion,Section 4,of this sp
10、ecification: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 D
11、ocuments2.1 ASTM Standards:2B243 Terminology of Powder MetallurgyC698 Test Methods for Chemical,Mass Spectrometric,andSpectrochemical Analysis of Nuclear-Grade Mixed Ox-ides(U,Pu)O2)C753 Specification for Nuclear-Grade,Sinterable UraniumDioxide PowderC757 Specification for Nuclear-Grade Plutonium Di
12、oxidePowder for Light Water ReactorsC859 Terminology Relating to Nuclear MaterialsC1233 Practice for Determining Equivalent Boron Contentsof Nuclear Materials1This specification is under the jurisdiction of ASTM Committee C26 onNuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.
13、02 on Fueland Fertile Material Specifications.Current edition approved Jan.1,2017.Published January 2017.Originallyapproved in 1976.Last previous edition approved in 2013 as C833 13.DOI:10.1520/C0833-17.2For referenced ASTM standards,visit the ASTM website,www.astm.org,orcontact ASTM Customer Servic
14、e 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 StatesThis international standard was developed in accordance
15、 with internationally recognized principles on standardization established in the Decision on Principles for theDevelopment of International Standards,Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade(TBT)Committee.1 E105 Practice for Probability Sampling
16、of MaterialsE112 Test Methods for Determining Average Grain Size2.2 ASME Standard:3ASME NQA-1 QualityAssurance Requirements for NuclearFacility Applications2.3 U.S.Government Documents:4USNRC Regulatory Guide 1.126 An Acceptable Model andRelated Statistical Methods for the Analysis of FuelDensificationCode of Federal Regulations Title 10,Part 50 DomesticLicensing of Production and Utilization FacilitiesCode of Federal Regulations Title 10,Part 71 Packaging andTransportation of Radioactive Materi