ASTM C757-2006(2011)e1 Standard Specification for Nuclear-Grade Plutonium Dioxide Powder Sinterable《核纯级可烧结的二氧化钚粉末的规格》.pdf

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1、Designation: C757 06 (Reapproved 2011)1Standard Specification forNuclear-Grade Plutonium Dioxide Powder, Sinterable1This standard is issued under the fixed designation C757; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year

2、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.1NOTESection 4.6 was changed editorially in June 2011.INTRODUCTIONThis specification is intended to provide the nuclear industr

3、y with a general standard for sinterableplutonium dioxide powder. It recognizes the diversity of manufacturing methods by which plutoniumdioxide powders are produced, and the many special requirements for chemical and physicalcharacterization that may be imposed by the end use of the powder in a spe

4、cific reactor system. It is,therefore, anticipated that the buyer may supplement this specification with more stringent oradditional requirements for specific applications.1. Scope1.1 This specification covers nuclear grade plutonium diox-ide, sinterable powder obtained by the oxalate precipitationr

5、oute, calcined above 500C, or any other equivalent processacceptable to the buyer. Included is plutonium dioxide ofvarious isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enricheduranium or by in-reactor neutron irradiation of recycled pluto-nium m

6、ixed with uranium.1.2 There is no discussion of or provision for preventingcriticality incidents, nor are health and safety requirements, theavoidance of hazards, or shipping precautions and controlsdiscussed. Observance of this specification does not relieve theuser of the obligation to be aware of

7、 and conform to all nationaland local regulations on processing, shipping, or using sourceor special nuclear materials. For examples in the U.S. Govern-ment, relevant documents are Code of Federal Regulations,Title 10 Nuclear Safety Guide, U.S. Atomic Energy Commis-sion Report TID-70162, and “Handbo

8、ok of Nuclear Safety”, H.K. Clark, U.S. Atomic Energy Commission Report, DP-5322.1.3 The PuO2shall be produced by a qualified process andin accordance with a quality assurance program approved bythe user.1.4 The values stated in SI units are to be regarded as thestandard.1.5 This standard does not p

9、urport to address all of thesafety concerns, if any, associated with its use. It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM Standards:3

10、C697 Test Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear-Grade PlutoniumDioxide Powders and PelletsC1233 Practice for Determining Equivalent Boron Contentsof Nuclear MaterialsC1295 Test Method for Gamma Energy Emission fromFission Products in Uranium Hexafluoride an

11、d UranylNitrate Solution2.2 ANSI Standard:ANSI/ASME NQA-1 Quality Assurance Requirements forNuclear Facility Applications42.3 U.S. Government Documents:Code of Federal Regulations, Title 10, Nuclear SafetyGuide, U.S. Atomic Energy Commission Report TID-701621This specification is under the jurisdict

12、ion of ASTM Committee C26 onNuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fueland Fertile Material Specifications.Current edition approved June 1, 2011. Published July 2011. Originally approvedin 1974. Last previous edition approved in 2006 as C757 06. DOI: 10.1520/C0

13、757-06R11E01.2Available from Superintendent of Documents, U.S. Government PrintingOffice, Washington, DC 20402.3For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the s

14、tandards Document Summary page onthe ASTM website.4Available from American National Standards Institute, 11 W. 42nd St., 13thFloor, New York, NY 10036.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.“Handbook of Nuclear Safety,” Clar

15、k, H. K., U.S. AtomicEnergy Commission Report, DP-53222.4 ISO Standard:ISO 8300 Determination of Pu Content in Plutonium Diox-ide (PuO2) of Nuclear Grade Quality, GravimetricMethod43. Isotopic Content3.1 Concentrations and homogeneity ranges of the pluto-nium isotopes shall be as specified by the bu

16、yer.3.2 The isotopic composition of the final product shall bedetermined by mass spectrometry and shall be reported on aweight basis.4. Chemical Composition4.1 Plutonium ContentThe minimum Pu content shall be86.0 weight % as sampled on the date of sampling and 87.5weight % after heating4hto950C.4.2

17、Uranium ContentThe uranium content of the pluto-nium dioxide shall be measured and reported on a plutoniumbasis.4.3 Americium ContentThe americium content shall bemeasured and reported on a plutonium basis. The maximumacceptable americium content shall be agreed upon betweenthe buyer and the seller.

18、4.4 The dates of analyses of U, Th and Am shall berecorded.4.5 Impurity ContentThe impurity content shall not ex-ceed the individual element limit specified in Table 1. Totalnon-volatile oxide impurity content excluding Am shall notexceed 6000 g/g Pu. If an element analysis is reported as “lessthan”

19、 a given concentration, this “less than” value shall be usedin the determination of total impurities.4.6 Equivalent Boron ContentFor thermal reactor use, thetotal equivalent boron content (EBC) shall not exceed 20.0g/g on a plutonium weight basis. For the purpose of EBCcalculation Eu, Dy, and Sm sha

20、ll be included in addition toelements listed in Table 1. The method of performing thecalculation shall be as indicated in Practice C1233. For fastreactor use, the above limitation on EBC does not apply.4.7 Gamma ActivityThe gamma activity (Bq/g Pu) of thegamma emitting fission products whose isotope

21、s have halflives of 30 days or greater shall be measured. The gammaradiation from fission products shall be less than 105MeVBq/g Pu.4.7.1 The list of nuclides and mean energies per disintegra-tion found in Test Method C1295 are to be used in thecalculations.5. Physical Properties5.1 Cleanliness and

22、WorkmanshipThe PuO2powder shallbe free of visible fragments of foreign matter.5.2 Particle SizeAll the PuO2powder shall be capable ofpassing a 100 m sieve and 95 % of the powder by weight shallbe capable of passing a 44 m sieve.5.3 Surface AreaThe specific surface area shall not be lessthan 5 m2/g a

23、nd not greater than 30 m2/g based on a Brunauer,Emmett, Teller (BET) adsorption method. See Notes 1 and 2.NOTE 1A specific surface area as low as 2 m2/g has been demon-strated to be acceptable when subsequently blended with other powder(s)of greater specific surface area. Therefore, powder with a sp

24、ecific surfacearea as low as 2 m2/g may be acceptable if agreed upon between thesupplier and the user.NOTE 2Consideration should be given to the compatibility of pow-ders with widely different surface areas within the intended process.6. Sampling6.1 Plutonium oxide is hygroscopic and can absorb suff

25、i-cient water during exposure to a moist atmosphere to causedetectable analytical errors. Sampling, weighing of the sample,and handling the sample shall be done under atmosphericconditions that do not alter the moisture or impurity content ofthe sample.6.2 The necessary chemical and physical analyse

26、s shall beperformed on portions of a representative sample taken fromeach lot.6.2.1 A lot is defined as the quantity of material that isuniform in isotopic, chemical, and physical characteristics.6.2.2 Lots may be formed by blending the powder to ensurehomogeneity within each lot.6.2.3 The mixing of

27、 two or more lots shall require theestablishment of a new lot.6.3 Sampling procedures, including the frequency and timeperiod for conducting analyses, shall be agreed upon betweenbuyer and seller in accordance with quality assurance require-ments.6.4 All sample containers shall be clearly identified

28、 by lotnumber and container number.6.5 The sample material shall be packaged so that noforeign material is introduced into the powder during storage orshipment.7. Methods of Chemical and Isotopic Analysis7.1 The analytical chemistry methods used shall be asdescribed in Test Method C697 or other meth

29、ods agreed uponbetween buyer and seller. See, for example, ISO 8300 fordetermination of Pu content in plutonium dioxide of nucleargrade quality.8. Quality Assurance8.1 Quality assurance requirements shall be agreed uponbetween buyer and seller. CFR Title 10, Part 50, Appendix 50and ANSI/ASME NQA-1 a

30、re referenced as guides.TABLE 1 Impurity Elements and Maximum Concentration LimitsElementMaximum Concentration Limitof Uranium, g/gPuBoron 3Cadmium 3CarbonA200Chlorine 300Chromium 200Fluorine 200Iron 300Gadolinium 3Nickel 100Nitride Nitrogen 200Thorium 200ASample may be heated prior to carbon analys

31、is.C757 06 (2011)129. Rejection and Rehearing9.1 Rejection and acceptance shall be by lot unless there isprior agreement to do otherwise between the buyer and seller.9.2 The buyer and seller shall agree to a third party as areferee in the event of a dispute in analytical results.10. Certification10.

32、1 The seller shall test the sample described in theSampling section to ensure conformance of the oxide to therequirements of the Isotopic Content, Chemical Composition,and Physical Properties Sections.10.2 The seller shall provide the buyer documents certifyingthat the oxide meets all the requiremen

33、ts of the IsotopicContent, Chemical Composition, and Physical Properties Sec-tions.10.3 The seller shall make available, as requested by thebuyer, records of all data from tests used to meet the require-ments in the Isotopic Content, Chemical Composition, andPhysical Properties Sections.11. Packagin

34、g and Package Marking11.1 Plutonium dioxide powder shall be packaged in sealedmetal containers to prevent loss of material and undue con-tamination from air or the container materials. The exact sizeand method of packaging shall be as mutually agreed uponbetween the buyer and the seller, and in conf

35、ormance with allapplicable regulations.11.2 Each metal container shall bear as a minimum a labelon the lid and side with the following information:11.2.1 Sellers name,11.2.2 Lot number,11.2.3 Gross, tare, net oxide weights,11.2.4 Plutonium weight, and11.2.5 A unique container reference number.12. Ke

36、ywords12.1 nuclear fuel; plutonium; plutonium dioxideASTM International takes no position respecting the validity of any patent rights asserted in connection with any item mentionedin this standard. Users of this standard are expressly advised that determination of the validity of any such patent ri

37、ghts, and the riskof infringement of such rights, are entirely their own responsibility.This standard is subject to revision at any time by the responsible technical committee and must be reviewed every five years andif not revised, either reapproved or withdrawn. Your comments are invited either fo

38、r revision of this standard or for additional standardsand should be addressed to ASTM International Headquarters. Your comments will receive careful consideration at a meeting of theresponsible technical committee, which you may attend. If you feel that your comments have not received a fair hearin

39、g you shouldmake your views known to the ASTM Committee on Standards, at the address shown below.This standard is copyrighted by ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959,United States. Individual reprints (single or multiple copies) of this standard ma

40、y be obtained by contacting ASTM at the aboveaddress or at 610-832-9585 (phone), 610-832-9555 (fax), or serviceastm.org (e-mail); or through the ASTM website(www.astm.org). Permission rights to photocopy the standard may also be secured from the ASTM website (www.astm.org/COPYRIGHT/).C757 06 (2011)13